Ms
MEERA VENKATESH
(INTERNATIONAL ATOMIC ENERGY AGENCY)
22/10/2018, 08:35
Host Country Representative
(India)
22/10/2018, 08:45
Ravi B. Grover
(Homi Bhabha National Institute (HBNI), Anushakti Nagar, Mumbai 400094, India)
22/10/2018, 09:00
For the past ten years, cumulative average growth rate for electricity generation in India has been close to 6%. During the year 2016-17, total electricity generation was about than 1430 billion kW-hour or TW-hour. It will be more than 1500 TW-hour in 2017-18. Considering rate of economic growth, linkage between economic growth and electricity requirements, increasing urbanisation and current...
Patrick Child
(European Commission)
22/10/2018, 09:30
Research and Innovation contributes to several of the ten priorities of the European Commission for 2015-19. The EU's energy research policy contributes, in particular, to provide its citizens and businesses with secure and affordable energy, while also addressing the causes of climate change.
The next Research and Innovation Programme, covering the period 2021-2027, will build on the success...
Nawal Prinja
(AMEC Foster Wheeler)
22/10/2018, 09:50
The time and cost of further increasing the overall readiness level of fusion energy, which requires testing materials under extreme environment, data collection, analysis and new designs, can be significantly reduced with the advent of the fourth industrial revolution. The fourth industrial revolution is on its way. Known as Industry 4.0, it represents the current trend to use automation and...
Arun Kumar Chakraborty
(ITER-India, Institute for Plasma Research)
22/10/2018, 10:45
The responsibilities of ITER-India include a mix of precision, heavy, R&D intensive and interface intensive systems, under built-to-print and functional systems category. In several systems, components fall under the category of first of its kind or of the largest kind. The uniqueness of specifications lead to a challenging situation – namely that neither the existing labs or potential...
Mr
Bernard Bigot
(ITER Organization)
22/10/2018, 11:10
ITER reached 50% completion of the work required to achieve First Plasma in November 2017. Progress has been made on ITER infrastructure since the 2016 FEC, most visibly the construction of many key buildings. The tokamak assembly building and the tokamak bioshield have been completed. The tokamak building will be ready for equipment in 2020. The cryogenic plant and the magnet power supply...
Dr
Emmanuel Joffrin
(CEA/IRFM)
22/10/2018, 11:35
Europe has elaborated a Roadmap to the realisation of fusion energy in which ‘ITER is the key facility and its success is the most important overarching objective of the programme’. We review the contribution of the recent JET experiments with the ITER first wall materials mix, and, the underlying physics understanding to mitigate the scientific risks identified in the ITER research plan....
Dr
Craig Petty
(General Atomics)
22/10/2018, 12:00
DIII-D research is addressing critical challenges in preparation for ITER and the next generation of fusion devices through a focus on scientific investigation of plasma physics fundamentals, integration of disparate core and boundary plasma physics, and development of attractive scenarios. Fundamental studies show that including the energetic particle “kick” model in transport codes...
Mr
SUNIL BELSARE
(INSTITUTE FOR PLASMA RESEARCH)
22/10/2018, 14:00
Plasma facing components (PFCs) of ITER-like tokamak are expected to subject high heat loads up to 10MW/m^2 during the tokamak operation in steady state condition. Selection of plasma facing materials/components required extensive qualification and testing for tokamak application. High Heat Flux Test Facility (HHFTF) plays an important role for the qualification and estimation of the life of...
Prof.
Troy Carter
(University of California, Los Angeles)
22/10/2018, 14:00
Studies of turbulence and transport in the Large Plasma Device (LAPD)
have: documented the role of drift-Alfvén waves and flows in avalanche
events; revealed a new instability in the edge of increased β plasmas;
and demonstrated an interaction between ICRF waves and edge
turbulence, leading to strong modulation of the former and enhancement
of the latter. Intermittent collapses of the...
Dr
Mayur Kakati
(Centre of Plasma Physics-Institute for Plasma Research, Sonapur, Assam, India)
22/10/2018, 14:00
It is important to understand how the plasma with unparalleled heat (~10MWm-2) and ion (~1024 m-2s-1) flux will interact with the tungsten walls in the ITER tokamak, more specifically at the Divertor region of the fusion machine. Several linear magnetized plasma devices have been developed worldwide that reproduced ITER Divertor like extreme conditions for studies on relevant plasma surface...
Dr
C. Craig Petty
(General Atomics)
22/10/2018, 14:00
Dr
Stanislas Pamela
(CCFE - UKAEA)
22/10/2018, 14:00
Edward Strait
(General Atomics)
22/10/2018, 14:00
Hiroshi Gota
(TAE Technologies, Inc.)
22/10/2018, 14:00
TAE's research has been devoted to producing a high temperature, stable, long-lived field-reversed configuration (FRC) plasma state by neutral-beam injection (NBI) and edge biasing/control. C-2U experiments have demonstrated drastic improvements in particle and energy confinement properties of FRC's, and the plasma performance obtained via ~10 MW NBI has achieved plasma sustainment of up to 5...
Dr
Jonathan Menard
(Princeton Plasma Physics Laboratory)
22/10/2018, 14:00
The spectrum of scientific and technological gaps that must be closed to achieve practical fusion energy using magnetically confined plasmas has been extensively documented. A common barrier to narrowing or closing these gaps is the scale and cost of fusion facilities needed to address the gaps. The low-aspect-ratio “spherical torus/tokamak” (ST) is being explored world-wide as a potentially...
Dr
Michael Komm
(Institute of Plasma Physics of the Czech Academy of Sciences)
22/10/2018, 14:00
In the years 2016-17 the research on the COMPASS tokamak was focused on support of solution of the key challenges for the design and operation of ITER and next-step devices. This included mainly installations and upgrades of state-of-art edge plasma diagnostics, such as the new divertor probe array and the High Resolution Thomson scattering. Strong emphasis was placed on development of...
Dr
Jonathan Menard
22/10/2018, 14:00
Bahukutumbi P. Radha
(University of Rochester)
22/10/2018, 14:00
Direct-drive (DD) inertial confinement fusion (ICF) offers a potential path for high yield and ignition. Two approaches – Laser Direct Drive (LDD), being pursued primarily at the OMEGA laser and the National Ignition Facility (NIF), and the Magnetized Liner Inertial Fusion (MagLIF), being pursued primarily at the Sandia National Laboratories, will be discussed in this talk. In LDD nominally...
Prof.
Wandong Liu
(University of Science and Technology of China)
22/10/2018, 14:00
The Keda Torus eXperiment (KTX) is a new built middle-size reversed field pinch (RFP) device at the University of Science and Technology of China. After the long time conditioning, the favorable wall condition is achieved for implementing experiment on KTX. In present, the maximum plasma current can reach 200kA, the discharge length is beyond 20ms and the duration of typical reversed field...
Prof.
Thomas Klinger
(Max-Planck Institute for Plasma Physics)
22/10/2018, 14:00
Mr
Min Xu
(Southwestern Institute of Physics)
22/10/2018, 14:00
Dr
James Harrison
(CCFE)
22/10/2018, 14:00
Mr
Rakesh Tanna
(Institute For Plasma Research)
22/10/2018, 14:00
Dr
Hendrik Meyer
(UK Atomic Energy Authority)
22/10/2018, 14:00
The ASDEX Upgrade (AUG) programme, jointly run with the EUROfusion MST1 task force, continues to enhance significantly the physics base of ITER and DEMO. Here, the full tungsten wall is a key asset for extrapolating to future devices. The high overall heating power and flexible heating mix and comprehensive diagnostic set allows studies ranging from mimicking the scrape-off-layer (SOL) and...
Dr
Hendrik Meyer
(UK Atomic Energy Authority)
22/10/2018, 14:00
Dr
Earl Marmar
(Mass. Inst. of Technology)
22/10/2018, 14:00
Dr
Tomohiro Morisaki
(National Institute for Fusion Science)
22/10/2018, 14:00
Dr
Gianluca Pucella
(ENEA)
22/10/2018, 14:00
Since the 2016 IAEA FEC Conference, FTU operations have been mainly devoted to experiments on runaway electrons and investigations about a tin liquid limiter; other experiments have involved the elongated plasmas and dust studies. The tearing mode onset in the high density regime has been studied by means of the linear resistive code MARS and the highly collisional regimes have been...
Dr
Emmanuel Joffrin
(CEA)
22/10/2018, 14:00
Prof.
Hyeon K. Park
(UNIST)
22/10/2018, 14:00
Dr
Nengchao Wang
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (IFPP), AEET, SEEE, CnHUST)
22/10/2018, 14:00
Recent J-TEXT research has highlighted the significance of the role that non-axisymmetric magnetic perturbations, so called 3D magnetic perturbation (MP) fields, play in fundamentally 2D concept, i.e. tokamak. In this paper, the J-TEXT results achieved over the last two years, especially on the impacts of 3D MP fields on magnetic topology, plasma disruptions, MHD instabilities, and plasma...
Masayoshi Sugimoto
(National Institutes for Quantum and Radiological Science and Technology)
22/10/2018, 14:00
Dr
Enrique Ascasibar
(CIEMAT)
22/10/2018, 14:00
Dr
Stefano Coda
(CRPP-EPFL)
22/10/2018, 14:00
Dr
John Kline
(LANL)
22/10/2018, 14:00
Arun Kumar Chakraborty
(ITER-India, Institute for Plasma Research)
22/10/2018, 14:00
pietro barabaschi
(f4e)
22/10/2018, 14:00
Dr
Guoqiang Li
22/10/2018, 14:00
Mr
Bernard Bigot
(ITER Organization)
22/10/2018, 14:00
Dr
Baonian Wan
(Institute of Plasma Physics, Chinese Academy of Sciences)
22/10/2018, 14:00
Dr
Hiroyasu Tanigawa
(Japan Atomic Energy Agency)
22/10/2018, 14:00
Mr
Nikolai Bakharev
(Ioffe Institute)
22/10/2018, 14:00
Dr
Baonian Wan
(Institute of Plasma Physics, Chinese Academy of Sciences)
22/10/2018, 14:25
Significant progress in the development of plasma control mechanism and understanding the related physics for steady-state advanced high-performance H-mode plasmas have been achieved on EAST since the last IAEA FEC in 2016. First demonstration of >100 seconds time scale long-pulse steady-state scenario with a good plasma performance (H98(y2) ~ 1.1) and a good control of impurity and heat...
Prof.
HYEON KEO PARK
(UNIST)
22/10/2018, 14:50
The KSTAR research efforts have been focused on expansion of the KSTAR operating space for ITER and K-DEMO[1], validation of critical physics and search of new physics. The operating regimes are high bp (up to ~2.8) non-inductive long pulse up to ~8s, high bN up to ~ 4.3, and k of ~2.16 and a long H-mode discharge over a minute. An improved underlying physics of resonant and non-resonant...
Dr
Earl Marmar
(Mass. Inst. of Technology)
22/10/2018, 15:15
Alcator C-Mod has been the only divertor tokamak in the world capable of operating at magnetic fields up to 8 T, equaling and exceeding that planned for ITER. Because of its relatively compact size, C-Mod accesses regimes of extreme edge power density (1 MW/m2 average through the surface of the plasma. H-modes on C-Mod have achieved world-record tokamak volume-average and pedestal plasma...
Dr
Masataka Nakahira
(JpQSTNFI)
22/10/2018, 16:40
This paper reports the completion of the first Toroidal Field Coil Structure (TFCS) of ITER of which Japan Domestic Agency (JADA) takes 100% share on procurement responsibility. The major technical challenges of the TFCS of ITER are (i) new material development for high ductility under cryogenic temperature (4K), (ii) application of partial penetration welding (PPW), (iii) welding deformation...
Dr
Yasuhisa Oda
(National Institute for Quantum and Radiological Science and Technology)
22/10/2018, 17:00
A. This paper presents a summary of recent progress pertaining to the manufacturing and inspection of ITER gyrotrons and their operation system in QST. Major achievements are as follows: (i) The final design of ITER gyrotron was accomplished and manufacturing of 2 ITER gyrotrons was finished. Then their factory acceptance test (FAT) in QST has started with ITER relevant high voltage power...
Dr
Yasuhisa Oda
(Japan Atomic Energy Agency)
22/10/2018, 17:10
As a part of in-kind contribution, India is responsible to deliver nine numbers (1 Prototype + 8 series production) of RF Sources to ITER system, each having power handling capability of 2.5 MW/CW at VSWR 2:1 in the frequency range 35 – 65 MHz or 3.0 MW/CW at VSWR 1.5:1 in the frequency range 40 – 55 MHz, along with other stringent requirements. As there is no such amplifier chain able to meet...
Dr
Yasuhisa Oda
(Japan Atomic Energy Agency)
22/10/2018, 17:15
The European 1 MW, 170 GHz industrial prototype CW gyrotron for ECRH&CD on ITER is a conventional (hollow-cavity) gyrotron, which is being developed by the European GYrotron Consortium (EGYC) in cooperation with the industrial partner Thales Electron Devices (TED), under the coordination of the European Joint Undertaking for ITER and the Development of Fusion Energy (F4E).
The CW industrial...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:20
A. Technologies for manufacturing of small and medium size Ion source (upto four RF driver) for positive and negative neutral beam systems have been evolved over last many decades and such ion sources are being successfully operated at various experimental facilities across the world. However, as the need arises for the larger size ion sources (eight driver) for ITER diagnostics and heating...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:30
The ITER Heating Neutral Beam (HNB) injectors, one of the tools necessary both to achieve burning conditions and to control plasma instabilities, are characterized by such demanding parameters as to require the construction of a test facility dedicated to their development and optimization.
This facility, called NBTF, is in an advanced state of realization in Padua (Italy), with the direct...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:35
For the ITER neutral beam (NB) system, a measure to achieve the 1 MV vacuum insulation of the beam source have been developed. For this purpose, design basis for 1 MV vacuum insulation has been developed by integrating previous empirical scaling for plane and coaxial electrodes and new scaling for area with locally-concentrated electric field. Consequently, as the measure, the beam source is...
Dr
Andrey Litnovsky
(Forschungszentrum Juelich, Germany)
22/10/2018, 17:40
Mirrors will be used as first plasma-viewing elements in optical and laser-based diagnostics in ITER. Deterioration of the mirror performance due to e.g. sputtering of the mirror surface by plasma particles or deposition of plasma impurities will hamper the entire performance of the affected diagnostic. Specialists Working Group on First Mirrors (FM SWG) in the Topical Group on Diagnostics of...
Dr
Eugene Mukhin
(Ioffe Institute)
22/10/2018, 18:00
This paper describes the benefits and challenges of divertor Thomson scattering 55.C4 (DTS) and laser-induced fluorescence 55.EA (LIF) integration in the divertor port #8 of ITER. One of the main challenges for the DTS system is to measure extremely low electron temperatures in the vicinity of the divertor plates. The cool and dense divertor plasma leads to pronounced collective effects and...
Prof.
Xiaoyu WANG
(Southwestern Institute of Physics)
22/10/2018, 18:20
As the testing mockup of tritium breeding blanket for DEMO, Chinese Helium Coolant Ceramic Breeder (HCCB) Test Blanket System (TBS) are under developing by China and will be tested in ITER to verify the key tritium breeding blanket technologies. After the approval of conceptual design by ITER Organization in 2015, the design optimization and more R&D activities for HCCB TBS have been under...
Dr
Subhash P.V
(ITER-India, Institute for Plasma Research, Gandhinagar, Gujarat)
23/10/2018, 08:30
Nuclear activation and subsequent radiological response of structural materials within fusion reactors like ITER and beyond need to be studied for operational, safety and radiological waste management reasons. The future fusion machines should be equipped with low radioactive materials optimized for expected neutron environment. Numerical tools with extended capabilities are needed for this...
Mr
Gheesa Lal Vyas
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
Charge eXchange Recombination Spectroscopy (CXRS) diagnostic shall provide the key measurement for ITER advance plasma control and physics studies. ITER CXRS-pedestal has a primary role of edge ion temperature, plasma rotation (toroidal and poloidal velocity) and impurity density measurements in the pedestal region (r/a=0.85 -1.0). Meeting the measurement requirements for these parameters in...
Mr
VENKATA NAGARAJU MUVVALA
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
Accelerators, Ion dumps and beam transport system for Neutral Beam application are designed to manage high heat loads in the range of 2-10MW/m2. The performance of these components under various damage criteria are assessed for their thermo-mechanical stability under various operating and faulty conditions. Due to the pulse nature (3s ON/ 20s OFF with 5 Hz modulation) of beam operation,...
Mr
Kaushal Patel
(Institute for Plasma Research)
23/10/2018, 08:30
In tokamaks, baking of vacuum vessel and first wall components is a prerequisite in order to obtain impurity free plasmas. Baking is performed to remove impurities viz. H2, H2O and Hydro-Carbon from the vessel and first wall components. ADITYA tokamak has been upgraded ADITYA-U tokamak to achieve shaped plasmas. The ADITYA-U is equipped with a comprehensive baking system for heating the SS...
Dr
Ivo Furno
(EPFL- CRPP)
23/10/2018, 08:30
Poster
The fundamental interactions between turbulent structures or blobs and suprathermal ions, injected by Li6+ beams in plasmas created by microwaves at 2.45GHz with ne~1015-1017m-3 and Te~2-10eV, are extensively investigated on the TORPEX toroidal device. Comparisons between fully validated numerical simulations and experimental 3D time-averaged suprathermal ion profiles reveal an entire spectrum...
Dr
Li Li
(Donghua University, Shanghai, China)
23/10/2018, 08:30
Poster
The plasma response to the 3-D external resonant magnetic perturbation (RMP) fields, applied for controlling type-I edge localized modes (ELMs) in ITER, is systematically computed in terms of the normal displacement of the plasma surface, in other words the 3-D corrugation of the plasma boundary. Five representative ITER H-mode plasma scenarios, ranging from an initial hydrogen plasma...
Dr
Yasuhisa Oda
(Japan Atomic Energy Agency)
23/10/2018, 08:30
Poster
Dr
Hiroyuki Tobari
(National Institute of Quantum and Radiological Science and Technology)
23/10/2018, 08:30
Technologies of DC 1 MV insulation with water and DC 1 MV vacuum insulation have been developed. As the result, manufacturing of DC 1 MV power supply components to produce 1 MeV negative ion beams have been completed for the ITER neutral beam test facility (NBTF). For the transmission line (TL), insulating tubes for hot and cooling water have been developed by clarifying resistivity of...
Dr
Masataka Nakahira
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
Poster
Ms
Elizabeth Tolman
(UsPSFC)
23/10/2018, 08:30
The ARC pilot plant conceptual design study [1] is extended to explore options for managing ~525 MW of fusion power generated in a compact high field ($B_0$ = 9.2 T) tokamak about the size of JET ($R_0$ = 3.3 m). Exploiting ARC’s demountable high temperature superconductor toroidal field (TF) magnets, poloidal magnetic field (PF) coils located inside the TF, and vacuum vessel (VV) immersed in...
Dr
Elena Gaio
(Consorzio RFX)
23/10/2018, 08:30
The JT-60SA satellite tokamak is now under advanced assembly phase in Naka (Japan). The majority of the new power supplies are provided by Europe, and the Italian National Research Council (CNR), acting through Consorzio RFX, has contributed in particular with two systems: the Quench Protection Circuits (QPC) for the superconducting magnets and the Power Supply System for RWM control.
The...
Mengdi Kong
(ChSPC)
23/10/2018, 08:30
Poster
Detailed experiments have been performed on TCV with its flexible electron cyclotron heating/current drive system to investigate reliable and efficient control of NTMs. For example, a novel sinusoidal sweeping technique has been studied in detail and we have shown for the first time that it is efficient for both NTM stabilization and preemption. This method is important for future devices as...
Prof.
Xiaoyu WANG
(Southwestern Institute of Physics)
23/10/2018, 08:30
Poster
Mr
Atsushi Kojima
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
Poster
Mr
Himanshu Tyagi
(ITER-India,IPR)
23/10/2018, 08:30
Indian Test Facility (IN-TF) [1] is being built in IPR to characterize Diagnostic Neutral Beam [2] in cooperation with ITER Organization. INTF is a complex system which consists of several plant systems like beam source, gas feed, vacuum, cryogenics and mechanical systems. To ensure successful operation INTF, integrated operation involving all the constituent plant systems is required. The...
Mr
Krishan Kumar Gotewal
(Institute for Plasma Research)
23/10/2018, 08:30
Remote Handling (RH) systems for maintenance and inspection of in-vessel components have been addressed in great detail for fusion machines around the world. Maintaining high availability of fusion machine and minimizing the maintenance time require robust and dependable RH systems. Such RH systems, being electro-mechanical in nature, requires research and development in various areas such as...
Mr
SIDDHARTH KUMAR
(ITER INDIA)
23/10/2018, 08:30
In the ITER, systems are classified in the different safety categories as per their function in the machine; Protection Important Components (PIC) needs more attention during the design and analysis for better safety margins. The French Nuclear Code RCC-MR (2007) is employed in the design, analysis and the manufacturing, applicable to the ITER protection important mechanical components. It is...
Dr
Anil Tyagi
(ITER-India, Institute for Plasma Research), Mr
Matteo Barbarino
23/10/2018, 08:30
Tungsten (W) will be used in ITER as a Plasma Facing Material (PFM) in divertor due to its capability to handle high heat flux while having a low Hydrogen (H) isotope affinity. However in presence of fusion neutrons and alpha particles, tungsten can accumulate radiation damage, which might significantly enhance its H retention property. In order to investigate the effects of radiation damage...
Mr
RAVINDER KUMAR
(ITER-INDIA,INSTITUTE FOR PLASMA RESEARCH)
23/10/2018, 08:30
For ITER Electron Cyclotron Emission (ECE) diagnostic, there is a requirement of high-temperature black body radiation source operating at atmospheric pressure. This source needs to be operated at high temperature (~ 500 0C) having a microwave emissivity > 0.95 in the frequency band 100-500 GHz, and > 0.75 for 500-1000 GHz. Moreover, the radiation surface should have temperature uniformity...
Dr
Tsuyoshi Kariya
(Plasma Research Center, University of Tsukuba)
23/10/2018, 08:30
Megawatt (MW) gyrotrons with a wide frequency range from 14 to 300 GHz are being developed in a collaborative ECH study for advanced fusion devices and a DEMO. (1) Detailed designs of a 14 GHz 1 MW gyrotron has been started for actual fabrication. For a 14 GHz RF beam with high divergence, a calculated transmission efficiency of 85% to the corrugated waveguide coupling position was initially...
Dr
Ryota Imazawa
(National Institutes for Quantun and Radiological Science and Technology)
23/10/2018, 08:30
The authors are demonstrating the key technology necessary for the ITER poloidal polarimeter (PoPola) in order to measure the plasma current profile in ITER. The entire optical train of a prototype channel was made to evaluate the performance of the laser alignment system and the stability of the polarization measurement. The PoPola system injects multiple far-infrared (FIR) laser beams into...
Dr
Andrey Litnovsky
(Forschungszentrum Juelich, Germany)
23/10/2018, 08:30
Poster
Mr
Alexey Razdobarin
(Ioffe Institute)
23/10/2018, 08:30
The performance of front-end elements of optical diagnostics in ITER under long-term operation and with limited access for their maintenance is in the focus of extensive R&D program involving laboratory study and testing in working tokamaks. The requirements to the front-end element design are driven by high-energy neutron and gamma radiation, intense particle fluxes and thermal loads at the...
Dr
Michael Komm
(Institute of Plasma Physics of the Czech Academy of Sciences)
23/10/2018, 08:30
Poster
Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and next–step devices, as it allows to convert the majority of the energy carried by charged particles through the scrape-off-layer (SOL) into isotropic radiation and thus avoids localized heat flux deposition in the divertor region. In order to maintain relevance to ITER and DEMO, a concentrated effort...
Mr
SRINIVASA MURALIDHARA
(ITER-INDIA)
23/10/2018, 08:30
The Auxiliary Cold Boxes (ACBs) of the ITER cryodistribution system has multiple cryogenic process volumes as well as interfaces with cryolines with isolated vacuum spaces. The cryogenic process volumes inside a single vacuum space have different temperature level, 4 K and 80 K as well as different operating pressure, 0.5 MPa and 1.8 MPa. The cryogenic process volumes including interfacing...
Dr
Carlo Sozzi
(Istituto di Fisica del Plasma - CNR, Milano, Italy)
23/10/2018, 08:30
Poster
Disruption prevention in the perspective of high performance, high current, long duration plasma discharges requires a substantial evolution of the schemes applied in most of the present tokamaks. An efficient prevention scheme requires the early identification of the nature of the off-normal behavior possibly leading to a disruption and the automatic selection of the appropriated...
Dr
Shinsuke Satake
(National Institute for Fusion Science, Japan)
23/10/2018, 08:30
Poster
The effect of magnetic perturbations on the rotation profile in tokamak has been studied both experimentally and theoretically, since the prediction and control of the plasma rotation is one of the key issues for the stable operation. The NTV torque caused by magnetic perturbations is evaluated by adopting either a local or global drift-kinetic models. In the local models, the finiteness of...
Dr
Jonathan Menard
(Princeton Plasma Physics Laboratory)
23/10/2018, 08:30
The Electromagnetic Particle Injector (EPI) has the potential for delivering the radiative payload to the plasma center on a 3-4 ms time scale, much faster, and deeper, than what can be achieved using present methods. Predicting and controlling disruptions is an important and urgent issue for ITER. While a primary focus is the early prediction and avoidance of conditions favorable to a...
Dr
Matej Mayer
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
Poster
During JET operation with all carbon walls prior to 2010 (JET-C) massive re-deposition of previously eroded carbon was observed in the divertor and in remote divertor areas. This massive carbon re-deposition was accompanied by a high retention of hydrogen isotopes trapped by co-deposition. Extrapolations of these results to ITER predicted very high potential tritium retention, resulting in the...
Dr
Masahiro Tanaka
(National Institute for Fusion Science)
23/10/2018, 08:30
The control and management of tritium in a fusion test facility is one of the important issues from the viewpoints of radiation safety and public acceptance. As for the tritium control in a fusion test device, understanding of tritium behavior in the exhaust gas would give us new knowledge into the characteristics of the tritium release and inventory. In the deuterium plasma experiment on the...
Mr
Nitin Bairagi
(Institute for Plasma Research)
23/10/2018, 08:30
The SST-1 cryostat houses 130 thermal shields cooled using liquid nitrogen, 16 toroidal field (TF) coils, 9 poloidal field (PF) coils and their associated support structures. Superconducting Magnets System (SCMS) of the SST-1 consisting of TF and PF coils is designed to cool with forced flow supercritical helium (SHe) at 4 bar (a), 4.5 K and a mass flow rate of 300 g/s using helium...
Dr
Matthew John Hole
(Australian National University)
23/10/2018, 08:30
Poster
In general, the operation of AC discharges in small tokamaks requires the control of a few external parameters such as vertical and horizontal fields, external heating (where available), chamber conditioning and gas puff. The dynamics and type of control used are mostly based on experimental empirical learning, with different combinations of actuators depending on the tokamak device....
Dr
Katsunori Ikeda
(JpNIFS)
23/10/2018, 08:30
Deuterium beam operation of the negative-ion-based neutral beam injector (N-NBI) was initiated in the Large Helical Device (LHD) in 2017. Both hydrogen (H) and deuterium (D) neutral beams were generated by changing the operation gas using the same accelerator. Comparison of the beam properties such as the extracted negative ion current and the co-extracted electron current, obtained with $\rm...
Dr
Chiara Piron
(ItRFX)
23/10/2018, 08:30
Poster
The fully non-inductive sustainment (“V_loop~0") of high normalized beta (“β_N”) plasmas is a crucial challenge for the steady-state operation of a tokamak reactor. In order to assess the difficulties associated with such scenarios, steady-state regimes have been explored on TCV using the newly available 1MW Neutral Beam Injection (NBI) system. Compared to the past [O. Sauter et al Phys. Rev....
Dr
Dmitriy Borodin
(Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung IEK-4: Plasmaphysik)
23/10/2018, 08:30
Poster
Beryllium (Be) erosion data is one of the key issues for ITER including the first wall (FW) life time predictions [1], which undergo a re-visit based on the recent studies at the existing devices: tokamak JET equipped with the ITER-like wall (ILW) and linear plasma device PISCES-B. The extrapolation of physical and chemically assisted sputtering data is based on interpretive and predictive...
Mr
Stefan Jachmich
(BeLPP)
23/10/2018, 08:30
Poster
Metallic first mirrors are essential plasma-facing components (PFC) in all optical spectroscopy and imaging systems used for plasma diagnosis. First Mirror Test (FMT) has been carried out at the JET tokamak with the ITER-like wall (JET-ILW). Over 120 test Mo mirrors were exposed in JET during the entire project. The aim is to provide an overview of results obtained for mirrors exposed during:...
Dr
Hyun-Tae Kim
(EUROfusion Consortium JET)
23/10/2018, 08:30
Poster
This paper presents the transport analysis of high density baseline discharges in the 2016 experimental campaign of the Joint European Torus with the ITER-Like Wall (JET-ILW), where a significant increase in the Deuterium-Deuterium (D-D) fusion neutron rate (~2.8 x 1016 sec-1) was achieved with stable high Neutral Beam Injection (NBI) powers of up to 28MW and low gas puffing.
Increase in...
Dr
Zhehui Wang
(Los Alamos National Laboratory)
23/10/2018, 08:30
Motivated by edge localized mode (ELM) control in H-mode plasmas, we summarize experimental and theoretical progress in MHD physics of plasma interaction with small pellets ranging from 10s of microns to a few mm in size. Layered spherical structures with a hollow core (“hollow pellets”) are attractive in comparison with solid spheres and gas puffing. Theoretical results based on multi-fluid...
Dr
Domenico Frigione
(ENEA)
23/10/2018, 08:30
Poster
Impact of low-mid Z impurity injection on plasma transport and confinement has been observed and reported in several Tokamak experiments. Understanding particle transport in mixed species plasmas is crucial for reactor relevant conditions where control of DT mixture along with control of He concentration will be necessary. In this paper we present the analysis of experimental electron density...
Dr
Ken Kajiwara
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
This report describes the key development of the ITER equatorial ECH/ECCD launcher (EL) for poloidal steering compatibility. The steering direction of the EL has been changed from toroidal to poloidal in order to enhance the current drive capability. The design modification is being progressed toward the design finalization in 2019.
The concept of upper launcher (UL) steering mechanism of...
Mr
Manoahstephen Manuelraj
(Institute for Plasma Research, Gandhinagar, Gujarat-382428, INDIA)
23/10/2018, 08:30
The plasma facing components (PFCs) in a tokamak are subjected to high heat flux and high temperature during plasma operation, which causes erosion of the first wall. There is also hot spot formation on the PFC due to physical phenomenon like thermal electron emission. In addition to fore-mentioned phenomenon, the events such as Edge Localized Mode (ELM), vertical displacement event (VDE) are...
Prof.
Igor Garkusha
(NSC KIPT)
23/10/2018, 08:30
Poster
Features of plasma energy transfer to the material surfaces during the plasma-surface interaction in presence of strong magnetic field are investigated within recently developed quasi-stationary plasma accelerator QSPA-M. This novel PSI test-bed facility is able to reproduce the ELM impacts, both in terms of heat load and particle flux to the surface, and to provide plasma transportation in...
Mr
David Schwörer
(Dublin City University, Ireland)
23/10/2018, 08:30
Poster
Filaments are field aligned, non-linear density perturbations, which
have been observed in most plasmas.
In tokamaks they can
carry a significant amount of particles and heat from the last
closed flux surface to the far scrape-off layer (SOL).
This highly non diffusive transport mechanism
can cause a
significant heat load onto first wall materials. It is
important to understand
the...
Mr
Narinder Pal Singh
(Institute for Plasma Research)
23/10/2018, 08:30
Acceleration Grid Power Supplies (AGPS) provides 8MW power at (-) 96kV to the beam source of DNB (Diagnostic Neutral Beam) and SPIDER (Source for Production of Ion of Deuterium Extracted from Rf plasma) for acceleration of negative ions with specific modulation. High Voltage Power supplies (HVPS) based on PSM (Pulse Step Modulation) topology has already demonstrated its ability for broadcast...
Dr
Alexey Dnestrovskiy
(NRC Kurchatov institute)
23/10/2018, 08:30
The steady state regime for tokamak based neutron source DEMO-FNS with parameters R/a=3.2 m/1m, B=5Т, Ip=4-5 MA, PNBI=30MW and РECR=6МW is studied using a consistent modeling of the central and divertor plasma. In our formulation, the divertor plasma state is determined by the values of heat flux PSOL and the pressure of the neutrals in the divertor pn. As boundary conditions for the central...
Dr
Eugene Mukhin
(Ioffe Institute)
23/10/2018, 08:30
Poster
Mr
Henri Weisen
(SPC EPFL)
23/10/2018, 08:30
Poster
Heat, particle and momentum confinement in L- and H-mode in deuterium (D), hydrogen (H) and in D/H mixtures have been investigated in JET. In L-mode (3T/2.5MA) at fixed density (2.5x10^19m^-3) a weak positive scaling of stored energy with ion mass, tau_Eth~A^0.15, is found [1], consistently with multi-machine scaling tau_Eth~A^0.2 [2]. Core temperature profiles are stiff with Ti~Te, and...
Mr
Ritesh SUGANDHI
(Institute for Plasma Research, Gandhiangar, India)
23/10/2018, 08:30
The Large Volume Plasma Device (LVPD) [1] is a cylindrical shaped pulsed plasma device dedicated in carrying investigations relevant to fusion and magneto-spheric plasma. For meeting requirements for its up gradation, efforts are in progress towards enhancing plasma duration (tpulse ~9-50ms), to cater need of controlled experiments on Electron Temperature Gradient(ETG) turbulence, a major...
Mr
Stefan Jachmich
(BeLPP)
23/10/2018, 08:30
Poster
The high thermal loads caused by a disruption of an ITER baseline scenario pulse potentially stored thermal energy of 350MJ and magnetic energy inside the vessel of 400 MJ pose a severe threat to the first wall components [1]. Massive gas injection (MGI) into a disrupting plasma has been shown to be capable of reducing the energy deposited onto the plasma facing components by increasing the...
Dr
Michael Drevlak
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
Poster
The ROSE code was written for the optimisation of stellarator equilibria. It
uses VMEC for the equilibrium calculation and several different optimising
algorithms for adjusting the boundary coefficients of the plasma. Some of
the most importand capabilities include optimisation for simple coils, the
ability to simultaneously optimise vacuum and finite beta field, direct
analysis of...
Mr
Deepak Aggarwal
(Institute for Plasma Research)
23/10/2018, 08:30
The tritium breeding blanket is the essential part of a fusion reactor which provides the tritium fuel self-sufficiency to the reactor. India under its breeding blanket R&D program for DEMO is focusing on the development of two breeding blanket concepts viz. Lead–Lithium cooled Ceramic Breeder (LLCB) and Helium Cooled Ceramic Breeder (HCCB). The study presented in this paper focuses on the...
Dr
Naohiro Kasuya
(Kyushu University)
23/10/2018, 08:30
Poster
Some experimental observations show poloidal asymmetry in the turbulence measurements, which can affect the plasma transport, so detailed spatial structures must be clarified. In Large Helical Device (LHD), an up-down asymmetry has been observed by the PCI diagnostic. Complicated configurations make it difficult to capture the entire structures of fluctuations in helical plasmas, so...
Dr
Carlos Hidalgo
(CIEMAT)
23/10/2018, 08:30
Poster
Turbulence spreading is the transfer of free turbulent energy from strongly driven (i.e., unstable regions) to weakly driven locations [1]. The net effect of this phenomenon is the radial redistribution of turbulent energy, modifying local plasma features. It has been pointed out that spreading may be important in setting the Scrape-Off Layer (SOL) width. The peak heat load onto the divertor...
Mr
Rajeshkumar Gajanan Trivedi
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
Poster
Dr
Sergei Gerasimov
(CCFE)
23/10/2018, 08:30
Poster
This paper presents an analysis of disruptions occurring during JET-ILW plasma operations covering the period from #80128 up to #92504. The total number of disruptions was 1951 including 466 MGI (massive gas injection), VDE (vertical displacement event) and Error Field Correction Coil experiments, which led to intentional disruptions; hence the average disruption rate is 16.1%. MGI has been...
Dr
David Brower
(University of California Los Angeles)
23/10/2018, 08:30
The International Tokamak Physics Activity (ITPA) Topical Group (TG) on Diagnostics has been conducting R&D activities to support improved ITER diagnostic performance. In this paper, highlights of the Topical Group activity are overviewed: mitigation of first mirror degradation in optical systems, mirror cleaning techniques have been progressed; in-vessel stray-light has been investigated to...
Mr
Rohitkumar Panchal
(Institute for Plasma Research)
23/10/2018, 08:30
At IPR, 1350 W at 4.5 K helium cryo plant is dedicated to facilitate the cooling requirements of SST-1 machine. Since 2004, helium refrigerator / liquefier (HRL) (Make: M/s. Air Liquide, France) is operational in mixed mode equivalent to 650 W (refrigeration power) and 200 lh-1 (liquefaction capacity) at 4.5 K. The HRL can be operated in two phase (1.3 – 1.5 bar (a) at 4.5 K – 4.7 K) as well...
Dr
Juergen Rapp
(Oak Ridge National Laboratory)
23/10/2018, 08:30
The Material Plasma Exposure eXperiment (MPEX) is a planned linear plasma device to address plasma-material interactions for future fusion reactors. Its concept does foresee the capability to expose apriori neutron irradiated material samples to fusion reactor grade divertor plasmas. This new capability will be unique world-wide addressing important research needs in the area of fusion nuclear...
Dr
Sergei Sharapov
(CCFE)
23/10/2018, 08:30
Poster
A deuterium-tritium (D-T) experimental campaign DTE2 on JET scheduled for 2019-2020,will be done in the Be/W vessel and will address essential operational, technical, diagnostic and scientific issues in support of ITER [1]. In preparation for the campaign, developments were performed on JET aiming at studies of alpha-particles. For studying AEs driven entirely by alpha-particles, a scenario...
Dr
Friedrich Schluck
(DeFJ)
23/10/2018, 08:30
Poster
Present-day fusion devices are operated with a multitude of diagnostics in different locations, with which important insight in plasma profiles is obtained. However, since the detected signals only represent a spatially small part of the machine, the experiment natively exhibits blind spots, in particular in the three dimensional edge plasma region, where flux surface averaging reductions are...
Dr
Brendan Lyons
(General Atomics)
23/10/2018, 08:30
Poster
An integrated-modeling workflow has been developed to predict equilibria and response to 3D magnetic perturbations in tokamak experiments. Starting from an equilibrium reconstruction from a past experiment, the workflow couples together the EFIT Grad-Shafranov solver, EPED model for pedestal stability, and NEO drift-kinetic-equation solver (for bootstrap current calculations) in order to...
Mr
SHIVAKANT JHA
(ITER-INDIA, IPR)
23/10/2018, 08:30
In ITER, plant Instrumentation & Control (I&C) components are exposed to harsh environment. Hence I&C for plant system is one of the most challenging requirements to fulfil the ITER demands. IN DA is responsible for the delivery of several diagnostics systems including (1) X-Ray Crystal Spectroscopy (XRCS) edge & survey to measure the plasma impurity for machine protection and basic control...
Dr
Laizhong Cai
(Southwestern Institute of Physics)
23/10/2018, 08:30
For a DEMO reactor, the first candidate material for plasma facing material(PFM) is tungsten(W) and current available structure material is reduced activation ferritic/martensitic (RAFM). And tungsten coating material is promising to be applied on first wall. Since chemical vapor deposition tungsten (CVD-W) has a higher density, less porosity and better thermal shock resistance, thick CVD-W...
Mr
Aditya Kumar Verma
(Institute For Plasma Research)
23/10/2018, 08:30
Experimental Helium Cooling Loop (EHCL) is a high pressure-high temperature helium gas system. EHCL is similar to the First Wall Helium Cooling System (FWHCS) of LLCB TBM and in this loop First wall mock ups up to one fourth (¼) size of TBM can be tested.
EHCL modelling consists of equipment arrangement, pipe routing, support, cable tray routing, instrumentation arrangement and tube...
Dr
HITESH KUMAR PANDYA
(Institute for Plasma Research)
23/10/2018, 08:30
The ECE Diagnostic system in ITER will be used to determine the electron temperature profile evolution, the high frequency fluctuation of the plasma electron temperature, the characterization of runaway electrons and the radiated power in the electron cyclotron frequency range (70-1000 GHz). These measurements will be used for advanced real time plasma control (e.g. steering the electron...
Dr
Takayuki Kobayashi
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
Development of the ECH/CD system for JT-60SA has been progressed. Successful results on the JT-60SA gyrotron development for multi-frequency, high-power, long-pulse oscillation such as 1 MW/100 s at both 110 and 138 GHz, 1.9 MW/1s and 1.5 MW/5s at 110 GHz, 1.3 MW/1.2 s at 138 GHz and 1 MW/1 s at 82 GHz were reported in IAEA FEC in 2014 and 2016. The development of the high-power, long-pulse...
Dr
Vanni Toigo
(Consorzio RFX)
23/10/2018, 08:30
Poster
Dr
Paritosh Chaudhuri
(Institute for Plasma Research)
23/10/2018, 08:30
Several materials have been developed and being investigated for reliable and sustainable breeder candidate material. Lithium meta-titanate (Li2TiO3) and Lithium ortho-silicate(Li4SiO4) are the prominent among the suitable candidate materials for breeders. India has proposed lithium meta-titanate (Li2TiO3) as the tritium breeder materials in the form of pebble bed for LLCB TBM. Li2TiO3 power...
Prof.
Mahendrajit Singh
(ITER - India Institute for Plasma Research Bhat Gandhinagar Gujarat 382428 India)
23/10/2018, 08:30
Indian Test Facility (INTF) is a R&D facility under development at Institute for Plasma research (IPR), Gandhinagar as a part of the neutral beam development from negative ion source (NNBI) program. The major advantage of the INTF besides developing the beams from large ion sources is to characterize and benchmark the ITER Diagnostic Neutral Beam (DNB) to the desired specifications over...
Dr
Gerd Gantenbein
(Karlsruhe Institute of Technology, Institute for Pulsed Power and Microwave Technology)
23/10/2018, 08:30
Poster
Mr
John Smith
(General Atomics)
23/10/2018, 08:30
Several key milestones have been completed recently in the fabrication of the Central Solenoid (CS) modules for ITER. The qualification coil has been completed and tested with many lessons learned that have now been incorporated into the processing of the production modules. Currently four modules are in production with the first module scheduled for completion in 2018 followed by full...
Dr
Atsushi Kasugai
(Japan Agency for Quantum and Radiological Science and Technology (QST), Rokkasho Fusion Institute)
23/10/2018, 08:30
The IFMIF project aiming at material tests for a future fusion DEMO reactor is under the EVEDA phase in the BA Agreement of fusion program between Japan and EU. As the accelerator activity, the installation and commissioning of the Linear IFMIF Prototype Accelerator (LIPAc) is at the second stage of demonstration of the feasibility of the low energy section of an IFMIF deuteron accelerator up...
Mr
Ondrej Ficker
(CzIPP, CzFNSP)
23/10/2018, 08:30
Poster
Runaway electrons (REs) as one of the yet unsolved threats for ITER and future tokamaks are a topic of intensive research at most of the tokamaks. The experiments performed on COMPASS are complementary to the experiments at JET and MST (Medium-Size Tokamaks), building on the flexibility of the diagnostics set-up and low safety constraints at this smaller (R0=0.56 m, a=0.23 m) device. During...
Mr
Rohit Anand
(ITER India , IPR)
23/10/2018, 08:30
ITER-India is responsible for delivery of 8+1(prototype) RF sources to ITER project. Each RF source will provide 2.5MW of RF power at VSWR 2:1 in the frequency range of 35 to 65MHz. Eight such RF sources will generate total 20MW of RF power. Two RF chains containing three high power amplifiers (HPA1, HPA2 and HPA3) need to be combined to build an RF source. HPA2 and HPA3 are RF tube based...
Dr
Larry R. Baylor
(Oak Ridge National Laboratory)
23/10/2018, 08:30
The technology of forming high-Z cryogenic pellets mixed with D2 that are shattered upon injection into a plasma has been developed at ORNL for mitigating disruptions and has been selected as the basis for the baseline disruption mitigation system on ITER. In these shattered pellet injectors (SPIs), large pellets of neon and argon mixed with D2 are formed from gas and are shattered upon impact...
Dr
Basil Duval
(Ecole Polytechnique Fédérale de Lausanne – Swiss Plasma Center (SPC), Association Euratom-Confédération Suisse(EPFL) CH-1015 Lausanne, Switzerland)
23/10/2018, 08:30
Poster
This paper presents a fresh attempt on TCV to optimise plasma breakdown in the break-less (45 micro-Ohm impedance) vacuum vessel culminating in a double breakdown and the formation of a doublet configuration. A statistical analysis of legacy single pole breakdown and early plasma current ramp failures helped modify vessel current estimators together with PSU command and control issues to...
Prof.
Christian Theiler
(EPFL-SPC)
23/10/2018, 08:30
Poster
The effect of magnetic geometry on scrape-off layer (SOL) transport and detachment behavior is investigated on the TCV tokamak with the goal of assessing the potential of alternative divertor geometries and for the validation of theoretical models. L-mode experiments reveal that increasing connection length and hence divertor volume by either increasing poloidal flux expansion or divertor leg...
Linda Sugiyama
(M.I.T.)
23/10/2018, 08:30
Poster
Small applied nonaxisymmetric magnetic fields have been demonstrated to have strong and complex effects on otherwise axisymmetric toroidal fusion plasmas. Their importance raises the question of the best ``steady state'' plasma configuration to use for their analysis. A steady state that is valid on fast time scales of a few Alfvén times is needed to invert and interpret experimental...
Ms
Abha Maheshwari
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
In-Wall Shield(IWS) Blocks will be inserted between inner and outer shell of ITER Vacuum Vessel. These blocks comprise of number of plates of Stainless Steel stacked together using fasteners of XM-19 and M30 size. Plates are tightened with pretension of 107 kN to withstand EM force of 1.83 × 104N during ITER operation. These bolts are spot welded with blocks to lock any type of rotation. There...
Dr
C Christopher Klepper
(Oak Ridge National Laboratory)
23/10/2018, 08:30
Poster
In preparation for JET Deuterium-Tritium Experiments 2 (DTE-2) and to assure readiness to provide fuel cycle-relevant measurements, the subdivertor fuel isotopic ratio detection limit, as determined by Penning optical gas analysis (OGA) [1, 2], was recently researched. Reevaluation of OGA data from DTE-1 [1] revealed a 1% uncertainty (error bar) at the 1% T/(H+D+T) concentration level. A...
Mr
Gautam Vadolia
(Institute for Plasma Research)
23/10/2018, 08:30
Hot Isostatic Press (HIP) equipment is basically an electric furnace which is contained in a pressure vessel. In HIP, the component is subjected to elevated temperature (generally over 1000 degree centigrade) and pressure (generally over 1000 bar) which results in fully isotropic material properties. As per 2012 estimate, approximately 1000 HIP systems have been installed worldwide. Around 50%...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
23/10/2018, 08:30
Poster
Mr
Alexey Vertkov
(SC "Red Star")
23/10/2018, 08:30
Poster
The modern results on the implementation of the Russian strategy in the development of designs of long-operating plasma facing element for steady state fusion reactors are considered and analyzed on an example of liquid metal limiters of tokamaks Т-15 and FTU. The experimental validation of this strategy is presented and results on liquid metal CPS behavior in tokamak conditions, effective...
Prof.
Gianmaria De Tommasi
23/10/2018, 08:30
Poster
For a burning plasma device like ITER, radiative power removal by seeded impurities will be inevitable to avoid divertor damage. Increasing divertor radiation by injecting low-Z impurities such as nitrogen, to reduce scrape-off layer heat flux and to cool the divertor plasma to detachment, is put forward as the primary method to achieve this goal. Here, the possibility of increasing the...
Dr
Thomas Schwarz-Selinger
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
Among many other favorable properties of tungsten its low intrinsic fuel retention makes it a promising candidate as plasma facing material. However, during operation defects in the tungsten lattice will evolve that will trap hydrogen isotopes. While for present day devices this increased retention is only limited to the near surface it will take place throughout the whole bulk in future...
Dr
Sergey Rogozhkin
(SSC RF ITEP of NRC “Kurchatov Institute”)
23/10/2018, 08:30
The reduced-activation ferritic-martensitic steel Eurofer 97 is the European benchmark structural material for in-vessel components of fusion reactor. Experimental data on neutron irradiated Eurofer 97 material have shown decrease in plasticity and radiation hardening at irradiation temperatures about 300 °C. Formation of dislocation loops and α' pre-precipitates is considered as the main...
Mr
Kiran PATEL
(Institute for Plasma Research)
23/10/2018, 08:30
The Bayard-Alpert (BA) type hot cathode ionisation gauge is widely used to measure neutral pressure precisely in vacuum system below 10-3 Torr pressure. Neutral pressure measurement in magnetic confinement fusion experiments is quite challenging for standard BA type gauge due to higher pressure limitation and its ionisation is affected by high magnetic and electrical fields. To overcome above...
Mrs
Valentina Huber
(Forschungszentrum Jülich GmbH)
23/10/2018, 08:30
Poster
The JET ITER-like wall (JET-ILW) combines plasma-facing components (PFC) made of bulk beryllium for main chamber limiter tiles and of bulk tungsten as well as tungsten coated CFC tiles for divertor tiles. The risk of damaging the metallic PFCs caused by beryllium melting or cracking of tungsten owing to thermal fatigue required a new reliable active protection system. To address this issue, a...
Prof.
Sanjeev Varshney
(ITER-India, IPR)
23/10/2018, 08:30
In the ITER, an important aspect of qualifying the components to the mandatory regulatory requirements, the system developers have a challenge to first design the components fulfilling guidelines of the ITER recommended French nuclear code RCC-MR (2007) and later on demonstrate to the regulator. It is even more involving for systems that are extending primary vacuum to the interspace and...
Mr
Deepak Sharma
(Institute For Plasma Research)
23/10/2018, 08:30
India is developing Lead-Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) for testing in ITER for the validation of fusion blanket design tools, tritium breeding performance and high grade heat extraction capability relevant to Indian DEMO. The LLCBTBM will be tested from the first phase of ITER operation (H–H phase) in one half of the ITER port no-2. LLCB TBM set consists of...
Dr
Riscob Bright
(Institute for Plasma Research)
23/10/2018, 08:30
Among the various lithium ceramics, Li2TiO3 is one which has been received much attention due to its very excellent properties, such as reasonable lithium atom density, low activation, excellent tritium release performance and chemical stability, etc. Lithium Titanate [Li2TiO3] pebbles with the diameter of 1mm was widely used for the experiments after successful completion of variety of...
Prof.
Ivan Kodeli
(Jozef Stefan Institute)
23/10/2018, 08:30
In the future fusion reactors, such as ITER or DEMO, tritium will be produced by bombardment of lithium atoms with neutrons and several types of special Tritium Breeder Modules (TBM) will be installed in the ITER reactor to demonstrate the self-sufficiency of tritium production. LiF pellets commercially produced as Thermo-luminescent detectors (LiF - TLDs) can be used to measure tritium...
Dr
Teresa Estrada
(CIEMAT)
23/10/2018, 08:30
Poster
Dedicated experiments have been carried out for a systematic comparison of turbulence and radial electric field measured at poloidally separated positions in the same flux-surface in the stellarator TJ-II. The rationale behind this study is twofold, verification of the spatial localization of instabilities predicted by the Gyrokinetic simulations in stellarators and verification of the...
Dr
Edilberto Sánchez
(Laboratorio Nacional de Fusión, CIEMAT)
23/10/2018, 08:30
Poster
In this contribution, recent simulations carried out in stellarator configurations with the global gyrokinetic code EUTERPE and the ongoing validation effort are presented.
The linear relaxation of zonal flows (ZFs) has been studied in global simulations in many stellarator configurations. The code has been verified by comparing results with both other gyrokinetic codes and analytical...
Dr
Susana Clement Lorenzo
(Fusion for Energy)
23/10/2018, 08:30
The ITER Remote Experimentation Centre (REC, [1]) in Rokkasho is one of the projects implemented within the Broader Approach (BA) agreement [2] as part International Fusion Energy Research Centre (IFERC). The long-term objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. On a shorter time scale, before ITER will be operated, the REC...
Mr
Pramit Dutta
(Institute for Plasma Research)
23/10/2018, 08:30
Tokamak inspection and maintenance requires different Remote Handling (RH) systems such as long reach planar manipulators, multi-DOF hyper-redundant arms etc. As no structural support can be provided inside the tokamak, these RH systems are usually cantilevered and have a number of articulations to traverse the toroidal geometry of the tokamak. The kinematic configuration is thus different for...
Guoqiang Li
(Institute of Plasma Physica, CAS)
23/10/2018, 08:55
The Chinese Fusion Engineering Test Reactor (CFETR), complementing ITER, is aiming to demonstrate fusion energy production up to 200 MW initially and to eventually reach DEMO relevant power level, to manifest high duty factor of 0.3~0.5, and to pursuit tritium self-sufficiency with tritium breeding ratio (TBR) > 1. The key challenge to meet the missions of the CFETR is to run the machine in...
Masayoshi Sugimoto
(QST-Rokkasho)
23/10/2018, 09:20
In this report, the latest results of the validation activities of the IFMIF/EVEDA project under the Broader Approach agreement are overviewed. For the Linear IFMIF Prototype Accelerator (LIPAc) to demonstrate the 9MeV/125mA D+ beam acceleration, the beam qualification study of the injector was completed with the emittance of 0.16 pi mm mrad smaller than required 0.3 pi mm mrad, and the...
Dr
Hiroyasu Tanigawa
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 09:45
The structural material development for the breeding blanket in a future fusion reactor is regarded as the most challenging technical issue due to the significance of 14 MeV DT fusion neutron irradiation that induces high displacement damage with a significant amount of the transmutation formed gas elements such as helium and hydrogen.
The strategy of fusion in-vessel structural material...
Dr
Philipp Lauber
(IPP Garching)
23/10/2018, 10:45
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
In 2017 a new scenario on ASDEX Upgrade for the dedicated investigation of energetic particle (EP) physics has been developed. This scenario is unique in two aspects: firstly, the neutral beam (NB) induced fast-ion beta is comparable to the background plasma β, and secondly, the ratio of the fast ion energy to the thermal background is of the order 100.
At ASDEX Upgrade we reach this...
Dr
Wei Shen
(Institute of Plasma Physics, Chinese Academy of Sciences)
23/10/2018, 11:05
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Oral
Instabilities driven by energetic particles including fishbones and Alfven eigenmodes, together with fast particle loss and redistribution due to resonant magnetic perturbations (RMPs), have been investigated numerically with codes M3D-K, MEGA, and GYCAVA in EAST tokamak. Firstly, hybrid simulations with the global kinetic-magnetohydrodynamic (MHD) code M3D-K have been carried out to...
Dr
Mario Podesta
(Princeton Plasma Physics Laboratory)
23/10/2018, 11:25
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
The inclusion of the reduced-physics energetic particle (EP) *kick model* for EP transport in TRANSP has resulted in a dramatic improvement of interpretive and predictive capabilities for time-dependent tokamak simulations including the effects of EP transport by instabilities. The kick model has recovered the measured toroidal Alfvén eigenmode (TAE) spectrum on NSTX-U and has reproduced...
Dr
Yasushi Todo
(National Institute for Fusion Science)
23/10/2018, 11:45
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Oral
Alfvén eigenmodes (AEs) driven by fast ions in tokamak plasmas and the fast ion distribution formed with the AEs, neutral beam injection (NBI), and collisions are investigated with hybrid simulations for energetic particles and a magnetohydrodynamic (MHD) fluid [1]. The multi-phase simulation [2], which is a combination of classical simulation and hybrid simulation, was applied for various...
Dr
Satoshi Yamamoto
(Institute of Advanced Energy, Kyoto University)
23/10/2018, 12:05
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
A. We discuss the effect of electron cyclotron heating (ECH) and current drive (ECCD) on fast particle (FP)-driven MHD instabilities in stellarator/heliotron (S/H) plasmas obtained in LHD, Heliotron J and TJ-II. We demonstrate that FP-driven MHD instabilities including energetic particle modes (EPMs) and Alfvén eigenmodes (AEs) can be controlled by means of magnetic shear s modified by...
Dr
Satoshi Yamamoto
(Institute of Advanced Energy, Kyoto University)
23/10/2018, 12:15
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
The helically-trapped energetic-particle (EP) driven resistive interchange mode (EIC) observed in the Large Helical Device (LHD) causes large amount loss of EPs. It is destabilized when the precession motion of the helically trapped EP resonates with the pressure driven mode. A velocity modulation caused by the toroidicity of the magnetic field produces this resonance. Strategy and the initial...
Dr
Guosheng Xu
(Institute of Plasma Physics, Chinese Academy of Sciences)
23/10/2018, 14:00
Poster
A highly reproducible stationary grassy ELM regime has been achieved in the EAST superconducting tokamak with water-cooled metal wall, exhibiting good energy confinement, H_98y2~1.1, strong tungsten impurity exhaust, and compatibility with low rotation, high density and fully non-inductive operations. It offers thus a highly promising operational regime in EAST, potentially applicable to...
Dr
Prashant Sharma
(ITER-India, IPR Gandhinagar)
23/10/2018, 14:00
Poster
Tungsten is a promising candidate for first-wall material in fusion reactors and its use as a plasma-facing material is being investigated in both tokamaks as well as laboratory experiments [1, 2]. In fusion environment tungsten will be exposed to neutron, helium and hydrogen isotope implantation along with the heat flux which will lead to material damage. Irradiation by charged particles such...
Dr
Jonathan Graves
(Ecole Polytechnique Federale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland)
23/10/2018, 14:00
Poster
The VENUS-LEVIS code [D. Pfefferle, *et al*, Compt. Phys. Communs. **185**, 3127 (2014)] has been optimised for full orbit and guiding centre simulations in fully 3D electromagnetic fields. Curvilinear flux coordinate systems are deployed, with analytic (Fourier) representation of the fields for accurate simulation over slowing down time scales of fast particles and heavy impurities. An...
Dr
Liang Wang
(Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP))
23/10/2018, 14:00
Poster
Managing excessively high divertor power and particle fluxes and related plasma-wall interactions (PWI) is one of the most critical issues for the steady-state operation of the EAST superconducting tokamak and future fusion devices, such as ITER and CFETR. A world record long pulse H-mode operation of 101.2 seconds with H_98=1.1 and total power injection of 0.3 GJ has been successfully...
Dr
Yawei Hou
(University of Science and Technology of China)
23/10/2018, 14:00
Poster
For burning plasmas in fusion reactors, Energetic Particles (EP) generated from plasma heating and D-T reaction can destabilize Alfven Eigenmodes (AE). Alfven eigenmodes can conversely induce transport and loss of energetic particles. It is one of the crucial issues to study the interaction between EPs and AEs for CFETR (China Fusion Engineering Test Reactor). Eigenanalysis of AEs in CFETR...
Mr
Udaya Maurya
(InIPR)
23/10/2018, 14:00
Poster
To achieve self-sustained ignited operation in a high energy Tokamak, it is important to understand and maximize the energy confinement time, which falls in the domain of transport theory. To analyze and understand dynamics of plasma in Tokamak, performing a one-dimensional transport simulation is still one of the best approaches. In our work we focus on burning plasma simulation and study the...
Dr
JYOTIRMOY PRAMANIK
(DEPT OF PHYSICS, KHARAGPUR COLLEGE)
23/10/2018, 14:00
Poster
Most of the tokamaks including ITER, a significant part of the plasma-facing component including diverters, limiters, etc is comprised with graphite material. In the fusion plasma environment, the graphite gets bombarded by hydrogen and its isotope (deuterium and tritium) ions and erode graphite to a significant extent. Since such carbon particles can retain large amounts of hydrogen, dust...
Gregorio Vlad
(ENEA, Fusion and Nuclear Safety Department, Frascati, Italy)
23/10/2018, 14:00
Poster
The results of a set of simulations of Alfvén modes driven by an energetic particle population are presented, with the specific aim of comparing energetic particle radial transport between single-n and multiple-n simulations. The hybrid reduced O($\epsilon^3_0$) MHD gyrokinetic code HMGC is used, retaining both fluid (wave-wave) and energetic particles nonlinearities. The code HMGC retains...
Dr
RYOSUKE SEKI
(National Institute for Fusion Science)
23/10/2018, 14:00
Poster
In the LHD, the fast ion confinement has been investigated by using three tangentially injected neutral beams (NBs) with 180 keV fast ions and/or two perpendicularly injected NBs with 40-80 keV fast ions. The Alfvén eigenmodes (AEs) are observed during the tangential-NB injections. The fast ion driven instabilities enhance the fast ion losses. It is important to identify the instabilities and...
Dr
Yasushi Todo
(National Institute for Fusion Science)
23/10/2018, 14:00
Poster
Mr
Shrishail Padasalagi
(ITER-India, IPR, HBNI)
23/10/2018, 14:00
Poster
The ECE diagnostic is planned to be used for the measurements of plasma electron temperature profile with good spatial and temporal resolutions. Secondary objectives are to obtain information on non-thermal electron populations and the power loss due to ECE.
One of the major requirements of ITER like Fusion Device is to study the plasma parameter to ascertain and control the fusion...
Dr
Defeng Kong
(Institute of Plasma Physics Chinese Academy of Sciences)
23/10/2018, 14:00
Poster
A non-stationary, effective edge localized modes (ELMs) mitigation / suppression regime has been recently obtained by counter NBI heating at high collisionality on the Experimental Advanced Superconducting Tokamak (EAST). Our results show that counter NBI can significantly enhance the reversed toroidal rotation as well as the E_r×B flow shear of the pedestal. With the increased E_r×B flow...
Mr
Montu Bhuva
(Institute for Plasma Research, INDIA)
23/10/2018, 14:00
Poster
A direct current (dc) plasma source consisting of hollow cathode geometry and a constricted anode is presented. The effect of a hollow cathode geometry on radial density distribution of a magnetized plasma column has been studied in a low-pressure (approximately 1.4Pa) argon discharge. The plasma column is characterized using Langmuir probe and the radial density distribution for two different...
Mr
Umesh Kumar
(Institute for Plasma Research, Gandhinagar, Gujarat, India)
23/10/2018, 14:00
Poster
A simple toroidal device (SMT) is a toroidal device in which plasma is
confined by the application of toroidal and vertical magnetic field only
resulting in absence of a conventional effective rotational transform. Such
devices provide a simple and well diagnosable test-bed for studies related
to equilibrium, fluctuations and particle confinement for Tokamak edge.
The device BETA at the...
Dr
Satoshi Ohdachi
(National Institute for Fusion Science)
23/10/2018, 14:00
Poster
Dr
Pengjun Sun
(Institute of Plasma Physics, Chinese Academy of Sciences)
23/10/2018, 14:00
Poster
Understanding plasma transport in phases with significant MHD activities (especially during plasma current ramp-up/down and disruption) in tokamak plasmas is crucial for predicting and thus controlling plasma behavior for future fusion devices, e.g. ITER. Since microturbulence plays an important role in driving anomalous plasma transport, the interactions between MHD modes and microturbulence...
Ms
Juan Huang
(CnIPPCAS)
23/10/2018, 14:00
Poster
On the EAST tokamak, one hundred seconds steady state H-mode (H98y2~1.1) discharge has been achieved by RF-only (LHW+ECRH+ICRH) heating with improvement of the auxiliary heating and current drive systems on actively cooled ITER-like mono-block tungsten divertor. Towards EAST high performance advanced state-steady operation regimes, fast-ion related physical issues become crucial for achieving...
Dr
Ralf Kleiber
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 14:00
Poster
Results from a hybrid approach (CKA-EUTERPE code) which couples an MHD code
with a gyrokinetic code are presented. Although perturbative, it offers a
relatively fast way to investigate the destabilisation of Alfven modes by
fast particles. TAE saturation amplitudes and their scaling with growth rate
and collisionality were investigated in a tokamak as well as in Wendelstein
7-X.
Full...
Dr
Manoj Kumar
(Institute for Plasma Research)
23/10/2018, 14:00
Poster
Plasma imaging is an essential diagnostics system for any tokamak as it can provide vital information on various plasma parameters. These systems are ones of the first diagnostics installed and are basic not only at start-up stage but also in subsequent operations. Imaging system generally consists of at least two cameras, one of them is a high speed camera and another one is slow speed...
Dr
Satoshi Yamamoto
(Institute of Advanced Energy, Kyoto University)
23/10/2018, 14:00
Poster
Mr
Prabhakar Srivastav
(Institute For Plasma Research, Bhat Gandhinagar India-382428)
23/10/2018, 14:00
Poster
Extensive measurements are carried out on micro turbulence because of their possible role in causing anomalous particle and energy transport in fusion devices [1]. Outcome from past investigations suggest that the Electron Temperature Gradient (ETG) driven turbulence is considered presently as a major source of anomalous plasma transport in fusion devices, as transport by ion scale turbulence...
Dr
Liqing Xu
23/10/2018, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Two types of kink modes, fishbone and long-lived mode are experimentally and numerically studied at EAST tokamak. In high β_{P} plasma, sawtooth instability was replaced by a saturated 1/1 internal kink mode which either manifests itself as a periodical burst energetic ion related fishbone or as a long-lived mode which is associated to the core safety factor at q_0~1. The present of those 1/1...
Ms
Meenakshee Sharma
(Institute for Plasma Research)
23/10/2018, 14:00
Poster
The cusp configuration reduces the plasma losses to boundary by diverging plasma to the narrow regions where the magnetic field lines intersect the wall. The efficiency of multi dipole cusp confinement depends on the plasma losses through cusp loss area, widely known as leak width. The Multi-line cusp Plasma Device (MPD) used electromagnets for plasma confinement and gives opportunity to vary...
Prof.
Didier Moreau
(CEA/DSM/IRFM)
23/10/2018, 14:00
Poster
Robust model-predictive control (MPC) algorithms based on extremely simple linear data-driven models have been recently developed for plasma kinetic control on EAST. This paper shows, for the first time, that MPC can be performed using a two-time-scale approximation, considering the kinetic plasma dynamics as a singular perturbation of a quasi-static magnetic equilibrium, which itself is...
Mrs
Himabindu Manthena
(IPR)
23/10/2018, 14:00
Poster
To solve the challenging problem of heat removal in a tokamak based fusion reactor, several advanced divertor configurations have been proposed and studied. We present here the reults of our studies of one of the more promising configurations, the X-divertor, conducted for the parameters of the Indian tokamak SST-1. Using the equilibrium code CORSICA, we develop the appropropraite magnetic...
Dr
Zhiyong Qiu
(Zhejiang University)
23/10/2018, 14:00
Poster
Gyrokinetic theory of nonlinear mode coupling as a mechanism for toroidal Alfv\'en eigenmode (TAE) saturation and thermal plasma heating in the fusion plasma related parameter regime is presented, including 1) parametric decay of TAE into lower kinetic TAE (LKTAE) and geodesic acoustic mode (GAM), and 2) enhanced TAE coupling to shear Alfv\'en wave (SAW) continuum via ion induced scattering....
Dr
Elena Belova
(PPPL)
23/10/2018, 14:00
Poster
Simulations of confinement-limiting Alfvén eigenmodes in the sub-cyclotron frequency range show a robust physical stabilizing mechanism via modest off-axis beam injection, in agreement with experimental observations from National Spherical Torus Experiment (NSTX-U). Experimental results from NSTX-U have demonstrated that neutral beam injection from the new beam sources with large tangency...
Mr
Chinmoy Mallick
(institute for Plasma Research)
23/10/2018, 14:00
Poster
Microwave discharge ion source (MDIS) is used in many applications including accelerators based neutron generators on suitable target through D_D or D_T fusion. The electromagnetic (EM) pump wave (ω_0) can propagate beyond cut off plasma density by changing its polarity and/or decomposing into different daughter waves through which it transfer its energy thus producing over dense plasma. Role...
Prof.
Thomas Klinger
(Max-Planck Institute for Plasma Physics)
23/10/2018, 14:00
The optimized superconducting stellarator device Wendelstein 7-X restarted operation after the assembly of a graphite heat shield and an inertially cooled island divertor. This paper reports on results from the first high-performance plasma operation. Plasma densities of $1-4\cdot 10^{19}\,\mathrm{m}^{-3}$ with electron temperature $5-10\,\mathrm{keV}$ were routinely achieved with hydrogen gas...
Mr
DHARMENDRA RATHI
(INSTITUTE FOR PLASMA RESEARCH)
23/10/2018, 14:00
Poster
Proper wall conditioning has turned out to be an essential element for achieving the highest possible plasma performance in present-day fusion devices. The main issues are controlling the generation of plasma impurities, liberated by plasma-surface interactions. Superconducting fusion machines need efficient wall conditioning techniques for routine operation in between shots in the presence of...
Dr
Annika Ekedahl
(CEA, IRFM)
23/10/2018, 14:00
Poster
Recent long pulse experiments in EAST have resulted in a new world record of 100 s long H-mode discharge, sustained by the radiofrequency (RF) systems, predominantly Lower Hybrid Current Drive (LHCD). In parallel, experiments in HL-2A have demonstrated successful LH wave coupling in H-mode plasmas with an ITER-relevant passive-active multijunction (PAM) LHCD launcher. These two achievements,...
Mr
Satadal Das
(Institute For Plasma Research)
23/10/2018, 14:00
Poster
The cross-field transport of electrons/ions across magnetic field is fundamentally important as it determinines the characteristics of plasma wetted area in the scrape of layer region and particle confinement in magnetically confined plasma devices. The electrically biased objects in the edge region inside tokamaks as well as in Linear plasma devices are known to influence the dynamics of...
Prof.
Leopoldo Soto
(Chilean Nuclear Energy Commission)
23/10/2018, 14:00
Poster
In a dense plasma focus (DPF) the plasma is compressed into a hot-warm dense pinch. Since, 50 years ago and during the first three decades the dense plasma focus (DPF) was studied as a possible device to produce dense transient plasmas for fusion research. The trend was to produce bigger devices over MJ stored energy and MA current through the plasma pinch, in order to increase the efficiency...
Dr
Pablo Garcia-Martinez
(CONICET - Centro Atomico Bariloche)
23/10/2018, 14:00
Poster
The interaction of energetic particles with MHD modes of different
types is a major concern for the next generation of experiments
involving burning plasmas. This issue arises in different contexts such as particle redistribution due to current driven instabilities (involving or not magnetic reconnection), activation of Alfven eigenmodes (AE) due to wave-particle interaction or loss of...
Dr
Mario Podesta
(Princeton Plasma Physics Laboratory)
23/10/2018, 14:00
Poster
Dr
Alessandro Biancalani
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 14:00
Poster
It is getting increasingly clear that many tokamak plasma phenomena which have traditionally been investigated separately, are actually intrinsically linked. One outstanding example along these lines - which is investigated in the present contribution - is the the interaction between Alfven modes (AM), turbulence, and zonal structures (ZS), like zonal flows and geodesic acoustic modes....
Dr
Hongda He
(Southwestern institute of physics)
23/10/2018, 14:00
Poster
The toroidicity-induced Alfven eigenmode (TAE) excited by energetic ions was first simulated by using GTC code based on HL-2A experimental configuration. The simulation results show that the fraction of energetic (fast) ions in HL-2A experiments is about 3%. The TAE eigenmode frequency is around 211 kHz and is inversely proportional to the square root of electron density, which is...
Ms
Jiraporn Promping
(Thailand Institute of Nuclear Technology)
23/10/2018, 14:00
Poster
Self-consistent simulations of plasma in a proposed tokamak design of Thailand Tokamak. (major radius = 65 cm, minor radius = 20 cm, plasma current = 100 kA, toroidal magnetic field = 1.5 T) are carried out using the 1.5D BALDUR integrated predictive modeling code. The simulations are used to investigate plasma transport with on and off axis positions of ion cyclotron resonance heating (ICRH)...
Dr
Wei Shen
(Institute of Plasma Physics, Chinese Academy of Sciences)
23/10/2018, 14:00
Poster
Dr
Yurii V. Yakovenko
(Kyiv Institute for Nuclear Research, Kyiv, Ukraine)
23/10/2018, 14:00
Poster
Results of simulations of the sawtooth-induced redistribution of fast ions in JET and ITER with the code OFSEF are presented. The dependence of the redistribution on the particle parameters (energy and pitch angle) is studied. The redistribution of the trapped and marginally passing particles is found to exhibit barrier-like behaviour at the separatrix between the trapped and passing...
Dr
Hao WANG
(National Institute for Fusion Science)
23/10/2018, 14:00
Poster
Energetic particle driven geodesic acoustic modes (EGAMs) in the Large Helical Device (LHD) plasmas are investigated using MEGA code. MEGA is a hybrid simulation code for energetic particles (EPs) interacting with a magnetohydrodynamic (MHD) fluid. In the present work, both the conventional and extended models of MEGA are employed. In the conventional model, only the EPs are described by the...
Dr
Philipp Lauber
(IPP Garching)
23/10/2018, 14:00
Poster
Mr
Antti Snicker
(Aalto University)
23/10/2018, 14:00
Poster
This contribution aims to broaden the understanding of the interplay between the internal and
external 3D perturbations on the fast ions in tokamak plasmas. At first, we used simulations
using the ASCOT suite of codes to analyze an ASDEX Upgrade discharge showing clear sign
of the interplay between a (3,2) neoclassical tearing mode (NTM) and external RMP coils on
the fast ion loss detector...
Dr
David Zarzoso
(CNRS)
23/10/2018, 14:00
Poster
Energetic particles naturally exist in a tokamak due to either fusion reactions or external heating such as ICRH or NBI. These energetic particles need to be well-confined in order to transfer their energy to thermal particles and achieve this way a regime with self-sustained fusion reactions. However, energetic particles excite modes that tend to de-confine the particles themselves. This is...
Dr
Ling Zhang
(CnIPPCAS)
23/10/2018, 14:00
Poster
In EAST tokamak, H-mode discharges have been obtained without a basic change at various heating conditions after installation of tungsten monoblocks at upper divertor. Recently, a reproducible long pulse H-mode operation with sufficient tungsten suppression has succeeded for both electron cyclotron resonance and lower-hybrid wave heated discharges and various experimental approaches are also...
488.
Verification and Validation of Integrated Simulation of Energetic Particles in Toroidal Plasmas
Zhihong Lin
(UC Irvine)
23/10/2018, 14:00
Poster
Energetic particle (EP) pressure gradients in fusion plasmas can readily excite mesoscale EP instabilities such as the Alfven eigenmodes (AEs) and energetic particle modes that drive large EP transport, which can degrade overall plasma confinement and threaten the machine’s integrity. EP could strongly influence thermal plasma dynamics including the microturbulence and macroscopic...
Dr
Tomohiro Morisaki
(National Institute for Fusion Science)
23/10/2018, 14:25
In the first deuterium (D) experiment, LHD established one of the most important milestones towards the realization of the helical fusion reactor, ion temperature Ti of ~ 10 keV. This is the highest record among stellarator/heliotron devices. Clear reduction of the ion thermal diffusivity in both core and edge regions in D discharge from hydrogen (H) was identified, indicating the effect of...
Dr
Enrique Ascasibar
(CIEMAT)
23/10/2018, 14:50
The flexibility of TJ-II together with its unique plasma diagnostics makes it an ideal laboratory to study the relationship between magnetic topology, electric fields, transport and model validation.
**Zonal flows and heat transport.** HIBP measurements of zonal electrostatic potential relaxation are consistent with EUTERPE gyrokinetic (GK) simulations. The width of the oscillating zonal...
Dr
Stanislas Pamela
(CCFE - UKAEA)
23/10/2018, 15:15
Future devices like JT-60SA, ITER and DEMO require quantitative predictions of pedestal density and temperature levels, as well as divertor heat fluxes, to improve global confinement capabilities while preventing divertor erosion/melting in the planning of future experiments. Such predictions can be obtained from non-linear MHD codes like JOREK, for which systematic validation against current...
Dr
Edward Strait
(General Atomics)
23/10/2018, 15:40
Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been demonstrated in US fusion research. Optimization of the current density profile has enabled passively stable operation without n=1 tearing modes in discharges simulating ITER’s baseline scenario with zero external torque. Stable rampdown of the discharge has...
Dr
Stefano Coda
(CRPP-EPFL)
23/10/2018, 17:05
The research program of the TCV tokamak ranges from conventional to advanced tokamak scenarios and advanced divertor configurations, to exotic plasmas driven by theoretical insight, exploiting the device’s unique shaping capabilities. The facility is operated intensively both domestically and with EUROfusion support. The new 1-MW NBI has expanded the parameter range, now encompassing ELMy...
Mr
Rakesh Tanna
(Institute For Plasma Research)
23/10/2018, 17:30
Ohmically heated circular limiter tokamak, ADITYA has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) having open divertor configuration with divertor plates. Experiment research in ADITYA-U (R0 = 75 cm, a = 25 cm) has made significant progress, since last FEC 2016. After successful commissioning of ADITYA-U, the Phase-I plasma operations have been conducted from December 2016, with...
Dr
Nikolai Bakharev
(Ioffe Institute)
23/10/2018, 17:55
Research of various aspects of tokamak physics is conducted on small tokamaks at Ioffe Insitute in a wide range of experimental conditions: R/a=1.6, Bt=0.5(1.0) T, Ip=250(500) kA – Globus-M(M2), R/a=2.4, Bt=1.0 T, Ip=150 kA – TUMAN-3M, R/a=7.0, Bt=3.0 T, Ip=25 kA – FT-2 tokamaks. Results obtained in final Globus-M experimental campaign (before upgrade shutdown) with the 25% toroidal magnetic...
Prof.
Gianmaria De Tommasi
(Università degli Studi di Napoli Federico II)
24/10/2018, 08:30
Poster
The JT-60SA is a superconducting tokamak device being built as a joint international project between Japan and Europe in the frame of the broader Approach agreement. One of the main goals of JT-60SA is to study practical and reliable plasma control schemes in view of the power plant. Plasma electromagnetic modelling is one of the essential tools for plasma operation in a fusion device and they...
Mr
AMITKUMAR PATEL
(INSTITUTE FOR PLASMA RESEARCH)
24/10/2018, 08:30
High temperatures inside tokamak for fusion research is achieved from auxiliary heating systems like neutral beam injectors (NBI), or RF heating devices, viz., ion cyclotron (IC), electron cyclotron and lower hybrid systems where High Voltage Power Supply (HVPS) is an essential requirement. ITER requires 20 MW of ICRF for heating and driving plasma current. A cascaded chain of amplifier is a...
Mr
Juro Yagi
(Institute of Advanced Energy, Kyoto University)
24/10/2018, 08:30
An advanced molten salt (AMS), in which powders of hydrogen-soluble and chemically reactive metals such as titanium are mixed, is investigated as a potential self-cooled breeding blanket material. It is shown that hydrogen isotope uptake in a vanadium plate in molten salt FLiNaK is suppressed by the addition of Ti powders into the salt. In addition, the corrosion of candidate structural...
Ms
Priti Kanth
(Institute for Plasma Research, HBNI)
24/10/2018, 08:30
Structural materials present in and round any fusion device will face stringent conditions due to the high-energy, high-intensity neutron emitted from the fusion plasma. This will have significant life-limiting impacts on the reactor components of both experimental and commercial fusion devices. The neutrons interact with the material initiating nuclear reaction leading to the production of...
Dr
Lijuan Hao
(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China)
24/10/2018, 08:30
Super Multi-functional Calculation Program for Nuclear Design and Safety Evaluation, SuperMC, is a full-function neutronics simulation software system including inner-coupled calculations among efficient radiation transport, depletion, activation and shutdown dose. Its advanced capabilities include CAD/image-based accurate modeling for complex irregular geometry, intelligent data analysis...
Mrs
Anita Patel
(Institute For Plasma Research)
24/10/2018, 08:30
Magneto Hydro Dynamic (MHD) phenomena plays an important role in governing liquid metal flow characteristics under strong transverse magnetic field and has, therefore, gained the attention of fusion community for the design of liquid breeder blankets. In presence of plasma confining toroidal magnetic field, the flow of electrically conducting liquid metal (Li/Pb-Li), typically used for coolant...
Mr
Agraj Abhishek
(Institute for Plasma Research)
24/10/2018, 08:30
Structural materials to be used in proposed fusion reactor will be exposed to hostile neutronic environmental conditions. These steels will interact with high energy neutron particles. The interaction is expected to degrade structural material properties such as loss of ductility, increase of yield strength and DBTT temperature. Artificial neural network (ANN) with back-propagation (BPN)...
Prof.
Hiroshi Yamada
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Energy confinement and thermal transport has been widely regarded as gyro-Bohm in tokamak as well as stellarator-heliotron for a single kind of ion. However, this gyro-Bohm model predicts confinement degradation in deuterium (D) plasmas because of larger normalized gyro radius than in hydrogen (H) plasmas, which conflicts with major experimental observations. This study aims to quantify a...
Ms
Shailja Tiwari
(Institute for Plasma Research)
24/10/2018, 08:30
Neutron Activation System (NAS) is the primary neutron diagnostics for Indian Lead-Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) in ITER. The main objective of NAS is to measure spatial distribution of neutron flux and energy spectra and in-situ measurement of tritium production rate inside the TBM. These measurements will be utilized for validation of neutron transport tools...
Dr
Keii Gi
(Research Institute of Innovative Technology for the Earth)
24/10/2018, 08:30
The Paris Agreement requires deep reduction of greenhouse gas emissions. The world is toward rapid transition not only for climate change mitigation but also for sustainable development. Fusion energy has outstanding characteristics of plentiful resources, no nuclear runaway and zero-carbon emission, and its development has made a remarkable progress thanks to large investment for more than 50...
Dr
Masahiro Kobayashi
(JpNIFS)
24/10/2018, 08:30
Poster
Significant core plasma transport improvement is observed in the detachment divertor operation, which is stabilized by application of resonant magnetic perturbation (RMP) to the edge stochastic layer of LHD. Pressure profile becomes peaked and the heat transport coefficient,chi_eff, estimated from transport analysis, reduced in the entire confinement region. The RMP amplitude scan experiments...
Dr
Kiyomasa WATANABE
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
We investigate the penetration threshold of the RMP (Resonant Magnetic Perturbation) by the external coils in the LHD (Large Helical Device) for the various configurations. In a configuration of the LHD, it has qualitative similar dependence with that in Ohmic tokamak plasmas. However, the qualitative dependence on the collisionality is opposite to that in a high plasma aspect configuration,...
Mr
Axat Patel
(Assistant Professor), Mr
Maulik Shah
(Assistant Professor)
24/10/2018, 08:30
High microwave power is generally measured and characterized by calorimetric dummy loads, which are designed to suit the exiting modes of the gyrotron / HPM. The output mode of the gyrotron is converted to a Gaussian mode-HE11 mode after passing through series of mode converters. The objective of this study is to design and fabrication of Calorimetric Dummy Load with efficient cooling medium...
Dr
Masayoshi Sugimoto
(JpQSTRFI)
24/10/2018, 08:30
The Linear IFMIF Prototype Accelerator aims to operate in Rokkasho Fusion Institute a 125 mA/cw deuteron beam at 9 MeV In order to prove the technical feasibility of the IFMIF accelerators concept.
A 2.45 GHz ECR ion source developed by CEA-Saclay is designed to deliver 140 mA/100 keV CW D + beam. The low energy beam transfer line (LEBT) relies on a dual solenoid focusing system to...
Mr
Yogesh Jain
(Institute for Plasma Research, HBNI)
24/10/2018, 08:30
A Passive Active Multijunction (PAM) antenna is designed and developed and would be commissioned on the ADITYA-U tokamak. The PAM antenna has many advantages over the grill antenna such as exhibiting a lower reflection coefficient at the plasma densities close to its corresponding cut-off density. The PAM antenna along with its transmission line components are designed to deliver RF power up...
Prof.
Jieqiong Jiang
(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China)
24/10/2018, 08:30
A high intensity D-T fusion neutron generator is an important experimental platform for research and development (R&D) of nuclear energy and nuclear technology applications. High Intensity D-T Fusion Neutron Generator (HINEG) has been developed by the Institute of Nuclear Energy Safety Technology (INEST), Chinese Academy of Sciences (CAS)/FDS team to perform researches on fusion nuclear...
Mr
Sachin S. Chauhan
(Department of Physics, Shri Vaishnav Institute of Technology and Science, Indore, India)
24/10/2018, 08:30
Based on the current trends in thermonuclear fusion research, it is quite likely that future fusion machines, DEMO and beyond, will be operating with tungsten and alloys based on tungsten as the plasma facing material on their walls and targets to dissipate the thermal as well as particle loads under extreme conditions. Tungsten is being preferred because of its superior thermo-mechanical...
Dr
Mukti Ranjan Jana
(Institute for Plasma Research)
24/10/2018, 08:30
Steady state Superconducting Tokamak (SST-1) has a provision for positive hydrogen ion based Neutral Beam Injector (NBI) to raise the tokamak plasma ion temperature ~ 1 keV with neutral hydrogen beam (Ho) power of 0.5 MW at 30 kV. Heart of NBI system is ion extractor system which consists of three grids each made up of OFHC copper. The beamlets originating from the extractor system is focused...
Dr
Hiroyuki Noto
(National Institute for Fusion Science)
24/10/2018, 08:30
The realization of advanced fusion reactors rests with improvement of cooling capacity of divertors. Enhancing mechanical properties of Cu alloys is one of the critical issues for the improvement. This paper reports development of dispersion strengthened Cu alloys using ball-milling, encapsulation, and Hot Isostatic Pressing (HIP) facilities. Cu-Al, Zr and Y alloys have been produced so far....
Dr
Tetsutarou Oishi
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Stochastization of edge magnetic fields has been extensively studied not only for the ELM mitigation but also for the plasma detachment and the impurity transport. The ergodic layer of Large Helical Device (LHD) consists of stochastic magnetic fields with three-dimensional structure intrinsically formed by helical coils. Reduction of the parallel impurity transport in the ergodic layer, so...
Mrs
Poulami Chakraborty
(Bhabha Atomic Research Centre, India)
24/10/2018, 08:30
In the present study, the effect of magnetic field on the corrosion of Indian Reduced Activation Ferritic Martensitic Steel (IN RAFMS) in flowing lead lthium eutectic (Pb-Li) has been studied in an electromagnetic pump driven loop (EMPPIL-M). The corrosion rate in the presence of of 0.5 KG magnetic field at a temperature of 773 K has been found to be 1.3 times higher than that observed in the...
Dr
Takashi Minami
(Institute of Advanced Energy, Kyoto University)
24/10/2018, 08:30
Poster
The effects of magnetic field topology on an electron internal transport barrier (eITB) and on its formation in the helical plasma are discussed in this paper. In helical plasmas, the eITB can be formed by generation of the positive radial electric field with electron cyclotron resonance heating due to the electron-root transition that is related to the neoclassical transport through the...
Mr
Chandra Sekhar Sasmal
(Institute for Plasma Research)
24/10/2018, 08:30
Indigenously developed India specific Reduced Activation Ferritic/Martensitic (IN-RAFM) steels are currently considered as a structural material for the Indian Lead Lithium cooled Ceramic Breeder Test Blanket Module (IN-LLCB TBM). Advanced ferritic/martensitic steels offer the opportunity for improvements in fusion reactor performance, operational lifetime and reliability, superior neutron...
Ms
Ranjana Gangradey
(Institute for Plasma Research)
24/10/2018, 08:30
Vacuum is an inherent part of any Fusion machine. The requirement of providing large pumping speed is growing as fusion science is progressing towards high temperature, high density, and large confinement machines. In its domestic programme of development of technologies for Fusion grade machines, Institute for Plasma research (IPR) developed the sorbent based cryopumps. Using coconut shell...
Prof.
Hitoshi Tanaka
(Kyoto University)
24/10/2018, 08:30
Poster
Electron cyclotron heating and current drive (ECH/ECCD) by electron Bernstein waves (EBWs) with multi-electron cyclotron resonances (ECRs) is carried out by injecting microwaves at two frequencies during the non-inductive start-up of a spherical tokamak (ST) . When the 2nd EBW at 5 GHz is excited in the non-inductively produced ST plasma with the 1st EBW at 2.45 GHz, plasma current is driven...
Dr
Kunihiro Ogawa
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Study on neoclassical and anomalous transport of energetic particle (EP) in the Large Helical Device (LHD) has been performed by means of escaping EP diagnostics. By starting deuterium operation of the LHD, confinement study of EPs has remarkably progressed by using newly developed comprehensive neutron diagnostics providing the information of EPs confined in the core region. Time evolution of...
Mr
Mayank Rajput
(Institute for Plasma Research)
24/10/2018, 08:30
Displacement per atom (dpa) in fusion reactor materials are essential designing parameters to ensure the reliable functioning and structural integrity of fusion reactor components. All probable reaction channels such as (n,n’), (n,2n), (n,p), (n,α) and (n,d) are open for the interactions of D-T neutrons of 14.1 MeV energy with the fusion reactor material. Evaluation of dpa requires energy...
Dr
Pratipalsinh A. Rayjada
(Institute for Plasma Research)
24/10/2018, 08:30
Er2O3 (erbia) is a leading candidate for hydrogen isotope barrier and electrical insulation coating application in some sub-systems of advanced nuclear fusion research reactor designs. Due to harsh environment of the reactor, structural and microstructural stability of the coatings at elevated temperature is critical. The polymorphs of erbia are reported in cubic, monoclinic and hexagonal...
Mr
Arnab Jyoti Deka
(Institute for Plasma Research)
24/10/2018, 08:30
ROBIN (RF Operated Beam source in India for Negative Ion research) is a negative H- ion source, which is operational in IPR, Gandhinagar. For measurement of various beam parameters such as beam energy, beam divergence, beam homogeneity and the stripping losses, Doppler Shifted spectroscopy diagnostics was established on ROBIN. The beam properties are studied by varying the source pressure...
Dr
Masaki Nishiura
(The University of Tokyo)
24/10/2018, 08:30
Poster
The dipole plasma exhibits strong heterogeneities in field strength, density, temperature, etc., while maintaining the holistic balance. Enquiring into the internal structures, we reveal the fundamental self-organizing mechanisms operating in their simplest realization (as commonly observed in astronomical systems) [1, 2]. Three new findings are reported from the RT-1 experiment: (i) Creation...
Prof.
Masayoshi Nagata
(University of Hyogo)
24/10/2018, 08:30
Poster
The Spherical Torus (ST) is a leading candidate for an advanced fusion reactor due to its compactness. Transient coaxial helicity injection (T-CHI) is one of CHI schemes, and it is used to generate and ramp-up the plasma current at the initial phase of a discharge. One of the most important issues in T-CHI is whether it can establish a current sufficient for succeeding current drive and...
Mr
Vinit Shukla
(ITER-India, IPR)
24/10/2018, 08:30
In the presently available fusion reactors, cryogenic helium is an integral part for cooling the magnets in order to achieve super conductivity. Some of the fusion reactors use tritium as a nuclear fuel along with deuterium, in which a part of tritium is proposed to be breeded through lithium blanket covering the first wall of plasma. Since fusion reactors have very small burn up efficiencies...
Dr
Masayuki Yoshikawa
(University of Tsukuba)
24/10/2018, 08:30
Poster
In the hot ion mode experiments of the tandem mirror GAMMA 10/PDX plasma, the suppression of drift-type fluctuation, which rotate in the direction of the electron diamagnetic drift, has been observed when the axial confinement potential is formed by the electron cyclotron heating (ECH) at the barrier (B) and plug (P) cells. The flute-type fluctuation of which rotation direction is the same as...
Dr
Hiroshi Idei
(Research Institute for Applied Mechanics, Kyushu University)
24/10/2018, 08:30
Poster
A transmission line and a launcher system have been newly developed to conduct the second (2nd) harmonic electron cyclotron (EC) plasma ramp-up with an eXtra-ordinary mode wave in the QUEST spherical tokamak. The incident elliptical polarizations were controlled with two corrugated (quarter/one-eighth wavelength) polarizers. The launcher system with two quasi-optical mirrors produced a sharply...
Dr
Hiroshi Tanabe
(University of Tokyo)
24/10/2018, 08:30
Poster
We present the latest results of high-resolution 2D imaging measurement of merging/reconnection heating during the central solenoid (CS)-free plasma startup of spherical tokamak using a new 96CH 2D ion Doppler tomography diagnostics. In the last decade, magnetic reconnection research made a major progress such as (a) achievement of $\sim$1keV plasma heating in MAST both for ions and electrons,...
Dr
Yasuhiro Suzuki
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
A topological change of the magnetic field structure on a transition phenomenon is investigated in the Large Helical Device (LHD). In the high-beta plasma experiment of the LHD, the spontaneous transition phenomenon is sometimes observed [1]. After the transition, the plasma density is increased and then the plasma stored energy is increased. One important observation after the transition is...
Dr
Asha Attri
(ITER-India, IPR)
24/10/2018, 08:30
The ion-solid interaction has fundamental importance and is a subject of evolving understanding for years. Energetic ions of energies eV to MeV are responsible for the kinetics in solids by transferring energy via elastic or inelastic interaction depending on the nature of the material. Tungsten is prime material to be used in future fusion devices because of its thermal and mechanical...
Dr
Kenji Tanaka
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
The positive isotope effects have been found in ECRH plasma of LHD. The enhancement factor of global energy confinement time (tauE) to ISS04 scaling in deuterium (D) plasma is about 17% better than in hydrogen (H) plasma. Ion scale density fluctuation level is higher in D plasma. Core fluctuation level in D decreases rapidly with increase of tauE.
Both tokamak scaling (ITER98y2) and...
Both tokamak scaling (ITER98y2) and...
Mr
Rameshkumar Joshi
(Institute for Plasma Research, India)
24/10/2018, 08:30
The Lower Hybrid Current Drive (LHCD) system has four klystrons, each rated for 0.5 MW, CW power at 3.7 GHz, which are employed to launch the lower hybrid waves into plasma [1]. VME and PXI based Data Acquisition and Control (DAC) system has already been implemented for the operation of LHCD System. VME based DAC system has been modified to incorporate measurement of RF Power signals.
The...
Mr
Žiga Štancar
(Jožef Stefan Institute)
24/10/2018, 08:30
The work presented in the paper is focused on the development of a multiphysics methodology for the creation of a realistic plasma neutron source for Monte Carlo neutron transport calculations. We begin with a description of the plasma neutron sources used in fusion neutronics so far – these are based on the assumption that the plasma is in thermal equilibrium, the neutrons being emitted...
Dr
Kensaku Kamiya
(QST, Naka)
24/10/2018, 08:30
Poster
Multiple turbulent plasma states in the edge transport barriers (ETBs) formation are studied on JT-60U. Following a slow transition, which causes significant reduction in the ion thermal transport in the pedestal towards the neoclassical level with a weak negative Er value, we found a clear and fast changes in the particle transport in association with the change in the Er towards a strong...
Dr
Makoto Kobayashi
(National Institute for Fusion Science)
24/10/2018, 08:30
In the Large Helical Device, deuterium plasma experiments began in March 2017 and completed in August 2017. In this experimental campaign, about $4×10^{18}$ neurons were generated and activated components in the torus hall. The concentration of radioactive isotopes in the components in the torus hall must be evaluated to estimate the radiation dose for workers and to plan the decommissioning...
Dr
Sejal Shah
(ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, India)
24/10/2018, 08:30
Neutron Irradiation impact on ITER grade insulating material
Sejal Shah1,4a, Sunil Kumar2, Sudhirsinh Vala2,4, R. Kumar2, M. Abhangi2, S. Prasad3, M. Bandyopadhyay1,4, A. Chakraborty1
1. ITER-India, Institute for Plasma Research, Bhat, Gandhinagar- 382428, India
2. Institute for Plasma Research, Bhat, Gandhinagar-382428, India
3. FCIPT Division, Institute for Plasma Research, Bhat,...
Mr
Gediminas Stankunas
(Lithuanian Energy Institute)
24/10/2018, 08:30
IFMIF-DONES (International Fusion Materials Irradiation Facility – DEMO-Oriented Neutron Source) is an accelerator based d-Li neutron source which aims at the qualification of materials at the irradiation conditions of a DEMO fusion power reactor as being developed in the frame of EUROfusion’s Power Plant and Technology (PPPT) programme. The high intense neutron radiation produced in the...
Mr
H. L. SWAMI
(Institute for Plasma Research)
24/10/2018, 08:30
The testing of the breeding blanket systems is one of the vital objectives of the ITER. It will generate the significant information for DEMO fusion reactor. ITER has assigned the three equatorial ports for testing of six blanket systems. In those six, there is a Test Blanket System (TBS) of India which is Lead Lithium Ceramic Breeder (LLCB) blanket system and it will be integrated into...
Dr
Gen Motojima
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Superior control of particle recycling and of plasma density has been established in the Large Helical Device (LHD) using greatly enhanced active pumping of the closed helical divertor (CHD). In-vessel cryo-sorption pumping systems inside the CHD in five out of ten inner toroidal divertor sections have been developed and installed step by step in LHD. The total effective pumping speed obtained...
Mr
Kumarpalsinh Jadeja
(Institute for plasma Research)
24/10/2018, 08:30
In ADITYA Upgrade, glow discharge wall conditioning (GDC) is performed for long hours after the tokamak plasma operation using H gas to control Oxygen and Carbon containing impurities. This leads to high retention of H gas on Graphite limiter and Stainless Steel (SS) vessel. Subsequently, high H outgassing rate requires increased pumping time and high H recycling during plasma discharges...
Dr
Elina Pajuste
(University of Latvia)
24/10/2018, 08:30
Novel method for determining the depth profile of tritium in metallic samples has been demonstrated. Tritium accumulation in the fusion reactor materials is considered as a radiological issue due to its radioactivity. Therefore, tritium behavior prediction and estimation of its overall retention in fusion devices is of high importance.
Proposed method in this study allows to measure depth...
Dr
Dobromir Panayotov
(FUSION FOR ENERGY)
24/10/2018, 08:30
Safety studies for fusion facilities are commonly conducted using codes originally developed for fission reactor accident analysis and adapted to model the fusion-relevant phenomena. Nevertheless there are many “fission developed” methods still not considered in fusion safety assessment which could offer significant advantages in the fusion power commercialization. Along with solving the...
Dr
Stefan Gerhardt
(Princeton Plasma Physics Laboratory)
24/10/2018, 08:30
The NSTX-U device began operation in 2016, producing 10 weeks of commissioning and scientific operations. However, a number of technical issues, including the failure of a key diverter coil, resulted in the suspension of operations. A comprehensive extent of condition review was initiated at the request of the Department of Energy; this paper will summarize the result of that process,...
Prof.
Kazuaki Hanada
(Advanced Fusion Research Center, Research Institute for Applied Mechanics, Kyushu University)
24/10/2018, 08:30
Poster
Out-flux of fuel particles from plasma-facing walls (PFWs) during long duration discharges on all-metal PFW QUEST is in agreement with a prediction of the hydrogen (H) barrier model we proposed [1]. A simple calculation based on the combination of rate equations of H state and the H barrier model predicts a significant impact in the response of plasma density. This result indicates that a...
Dr
Jyoti Shankar Mishra
(Institue for plasma research)
24/10/2018, 08:30
High density plasma operation with centrally peaked profile is one of the key aspects in achieving break-even condition in magnetically confined fusion devices. In this prospect an efficient fuelling method capable of supplying particles into the core of the plasma is desired. Till date, cryogenically solidified pellets of hydrogen isotopes have been proved as an efficient method of...
Mr
SUDHIRSINH VALA
(INSTIUTE FOR PLASMA RESEARCH)
24/10/2018, 08:30
The Fusion Neutronics laboratory at Institute for Plasma Research (IPR), Gandhinagar, India has indigenously developed an accelerator based 14-MeV neutron generator for fusion neutronics studies for material development under Indian Fusion program. This neutron generator is producing neutron yield of $10^{10}$ n/s and it will be further upgraded to the $10^{12}$ n/s. It consists of a 2.45 GHz...
Ms
Pujita Bhatt
(Senior Research Fellow)
24/10/2018, 08:30
In high microwave power applications like gyrotron, transmission line system, calorimetric dummy load, etc, requires design, modeling, simulation and evaluation of transmission line system before fabrication of the same is undertaken. Under the aegis of Department of Science and Technology (DST), a multi-institutional program for the development of a gyrotron operating at 42±0.2GHz/200kW/3secs...
Dr
Akira Ejiri
(Graduate School of Frontier Sciences, The University of Tokyo)
24/10/2018, 08:30
Poster
Plasma current start-up without a large flux swing by the central solenoid is a critical issue in fusion research. The lower hybrid wave (LHW) is known to be an effective current drive tool in conventional tokamaks, and it is used in the TST-2 spherical tokamak (ST) device. The TST-2 device provides a unique opportunity to compare outboard-launch and top-launch schemes for plasma current...
Prof.
Viacheslav Chernov
(A.A.Bochvar High-technology Research Institute of Inorganic Materials (SC "VNIINM"))
24/10/2018, 08:30
The structure and physical-mechanical properties of the metal structural materials (SM) with BCC (ferrite-martensitic steels, alloys of vanadium, etc.) and FCC (austenitic steels, etc.) crystal lattices in the conditions of “before-after-during” low-temperature irradiation were analyzed. The qualitative and quantitative distinctions of the states and properties of SM “before-after” (an...
Dr
Tokihiko Tokuzawa
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
We report the discovery of rapid momentum change and oscillatory flow as a result of the pellet injection. Novel diagnostics tools with high spatio-temporal resolution applied to the perpendicular flow velocity and turbulence intensity measurements in LHD experiments show the following results. Just after the pellet injection, (1)the damped oscillating flow velocity and the increasing density...
Mr
ROHIT KUMAR
(Institute For Plasma Research)
24/10/2018, 08:30
The ADITYA-U tokamak (R0 = 0.75 m, a = 0.25 m) is designed to have shaped plasmas in both single and double null diverter configurations. It is quite well known that sustaining a shaped plasma in tokamak requires very good plasma column position control, both horizontal and vertical. A proportional–integral–derivative (PID) based control system has been designed and operated to achieve...
Prof.
Yonghua Ding
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (IFPP), AEET, SEEE, CnHUST)
24/10/2018, 08:30
Poster
Controlling the tearing mode (TM) is one of the major topics of fusion research, since TM degrades the plasma confinement and even induces major disruption if it is locked. Previous experimental and theoretical studies showed that the resonant magnetic perturbations (RMPs) influence both the rotation and width of the TM. As a result, the static RMP could apply a net stabilizing and braking...
Mr
ArunPrakash Arumugam
(Institute for Plasma Research, Bhat, Gandhinagar, India)
24/10/2018, 08:30
Steady state Superconducting Tokamak (SST-1) is a large aspect ratio Tokamak with a major radius of 1.1 m and minor radius of 0.20 m. Plasma Facing Components (PFC) is one of the major sub-systems of SST-1 Tokamak. Plasma Facing Components of SST-1 consists of divertors, passive stabilizers, baffles and poloidal limiters. PFCs are designed and fabricated to be Ultra High Vacuum (UHV)...
Dr
Takuma Wakatsuki
(National Institutes for Quantum and Radiological Science and Technology)
24/10/2018, 08:30
Poster
Safety factor profile control via active feedback control of electron temperature profile during a plasma current ramp-up phase of a DEMO reactor is investigated to minimize the magnetic flux consumption of a central solenoid (CS) for wide range of *q* profiles. It is shown that *q* profiles with positive, weak and reversed magnetic shear can be obtained with less than half of the empirical...
Prof.
Yasushi Ono
(University of Tokyo)
24/10/2018, 08:30
Poster
The high-power reconnection heating of ST plasma has been developed in TS-3U, TS-4U and MAST experiments, leading us to direct access to burning plasma. This unique method is caused by the promising scaling of ion heating energy that increases with squire of reconnecting magnetic field B_rec. We studied mechanisms for this B_rec^2-scaling of reconnection (ion) heating mainly using TS-3U...
Dr
Arakcheev Aleksey
(Budker INP)
24/10/2018, 08:30
Experiments simulating the pulsed heat loads expected in the ITER divertor were carried out at the BETA facility in the Budker Institute. Using a pulsed electron beam with a duration of 0.2-0.3 ms and heat load with a heat flux factor HFF ≈ 30 MJ m-2s-0.5 below the melting point of tungsten were obtained. A distinctive feature of BETA is the ability to study the processes of erosion of...
Mr
Kunal Bhatt
(ITER-India, Institute for Plasma Research)
24/10/2018, 08:30
ITER cooling waters system consists of large piping network to remove the heat load of about 950MWatt through various branched connections. Many of the branches are connected to main pipes by half coupling full penetration weld joints. There is requirement is to have full penetration for all the joints however quality classification (QC-2), recommends only 10% testing of the total weldment. In...
Dr
Shyamkumar Khambholja
(B & B Institute of Technology, Vallabh Vidyanagar, Gujarat, India)
24/10/2018, 08:30
Lead-Lithium (Pb-Li) alloy in its eutectic composition is one of the promising candidates to be used as liquid blanket in fusion reactor. Helium cooled Lead Lithium (EU-HCLL), Dual cooled Lead Lithium (US-HCLL), Indian LLCB are some of the concepts being explored worldwide for future fusion reactor [1]. In this scenario, the characterization of Pb-Li alloy becomes important to gainfully...
Dr
Premjit Singh Kongkham
(Institute for Plasma Research)
24/10/2018, 08:30
This work summaries the experimental studies on joining of tungsten based refractory materials at high temperature using vacuum brazing process. The objective of the joining of these refractory materials is to develop the joining technique for fabricating helium cooled divertor target relevant to DEMO fusion reactor. These so called - divertor fingers - are expected to handle the incident heat...
Dr
Yuki Takemura
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
The frequency slowing-down mechanism of the locked-mode-like instability without a large
magnetic island is investigated for the first time, based on the LHD experimental analysis.
The slowing-down frequency is caused by two processes. One is the resonant surface moving
to the small E × B rotation frequency region and the other is the slowing-down E × B rotation
frequency around the...
Mrs
Bharathi Magesh
(Institute for plasma research)
24/10/2018, 08:30
The detection of a peak corresponding to a hydrogen bearing impurity species (mostly due to water vapour :H20) was reported many times in past while performing the Doppler shift spectroscopy (DSS) diagnostics in several neutral beam injectors based on positive ion sources. However, for the experiments based on negative ion sources, we are reporting the detection of this peak for the first...
Dr
Felipe Bedoya
(MIT-Plasma Science & Fusion Center)
24/10/2018, 08:30
Conditioning of Plasma Facing Components (PFC) is a common practice to improve the plasma performance in both tokamaks and stellarators. The evaporation of thin Li films on the PFC and first wall has given positive results in multiple machines (CDX-U, LTX, TFTR, NSTX, EAST). Reduced recycling and impurity concentration in the plasma are commonly associated with Li. As a consequence, improved...
Dr
Naomichi Ezumi
(University of Tsukuba)
24/10/2018, 08:30
Poster
In Plasma Research Center, University of Tsukuba, divertor simulation experiments have been conducted at the end region of GAMMA 10/PDX. The high temperature end loss plasmas of GAMMA10/PDX are a functional tool for simulating edge and divertor plasmas and contribute to developing a deeper understanding of the physics involved in plasma detachment. Our aim is to study detachment phenomena...
Dr
Jin Myung Park
(Oak Ridge National Laboratory)
24/10/2018, 08:30
Physics based simulations using a new integrated 1.5D core-edge approach for a whole device modeling capability project a compact net electric fusion pilot plant is possible at modest scale based on the advanced tokamak concept, and identify the key parameters for its optimization. These first of a kind reactor simulations provide new insights cf. previous “systems code” projections by...
Dr
Shinsuke OHSHIMA
(Kyoto University)
24/10/2018, 08:30
Poster
The hydrogen/deuterium (H/D) isotope effects on fluctuations and its configuration dependence are studied in a helical device, Heliotron J. The isotope dependence of a toroidally symmetric fluctuation in low frequency range of <~4kHz,, which is considered as a zonal flow, is observed in low-density ECH plasmas in Heliotron J. The long-range toroidal correlation of the low frequency range...
Dr
Christian Day
(Karlsruhe Institute of Technology)
24/10/2018, 08:30
In the framework of the EUROfusion Programme the EU is preparing the conceptual design of the fuel cycle for a pulsed fusion DEMO. Over the last years, a completely novel and most innovative fuel cycle architecture has been developed, driven by the need to reduce the tritium inventory to an absolute minimum.
To achieve this goal, batchwise processes used in the fusion fuel cycle so far were...
Dr
Sterling Smith
(General Atomics)
24/10/2018, 08:30
Spin Polarized Fusion (SPF), which increases the DT fusion cross section by 50% and is predicted to yield power gains of 75% in an ITER Q=10 plasma (without SPF), could be demonstrated in the DIII-D tokamak, using recent technological advances. The cross section (probability) for thermal DT fusion is not only temperature dependent, but also depends on the spin orientation of the nuclei,...
Mr
Sayantan Mukherjee
(Kalinga Institute of Industrial Technology,Bhubaneswar,Odhisa(India))
24/10/2018, 08:30
The thermal performance of plasma facing components in a fusion reactor receiving high heat fluxes could be enhanced significantly by using nanofluid which are suspensions of 0.001-10% nanoparticles of <100nm size. Nanofluids show a promising heat transfer enhancement compared to the base fluid. Water-based nanofluids have the potential to deliver much improved high heat flux cooling while...
Mr
Samiran Shanti Mukherjee
(Institute for Plasma Research)
24/10/2018, 08:30
Cryoadsorption cryopump with large pumping speeds application has been developed at the Institute for Plasma Research (IPR). These pumps are cooled with liquid helium for cryopumping panels below temperature 5K to adsorb hydrogen and helium gases and with gaseous helium for thermal shields at around 80 K during fusion reactor relevant applications. The panels are coated with activated carbon...
Mrs
Deepti dubey
(ITER-India, IPR, Bhat, Gandhinagar, 382428, Gujarat, India)
24/10/2018, 08:30
An accelerator based 14 MeV neutron source is under development to study the fusion neutronics for Indian fusion programs. The neutrons are generated by impinging 10 mA deuterium beam accelerated up to 340 keV energy over a 140 Curie tritium target. Being a system handling tritium-radio-active material, a recovery system is to be designed to minimize airborne tritium effluent releases to well...
Mr
Timur Tulenbergenov
(Institute of Atomic Energy of National Nuclear Center)
24/10/2018, 08:30
The research goals are determining the effect of nitrogen plasma on the tungsten and comparative analysis of the formation of tungsten fuzz on the helium plasma interaction on the initial surface of tungsten and on the surface of tungsten, previously subjected to nitriding. The experiments were carried out on an imitation stand with a plasma-beam installation. The device provides the following...
Dr
Yasunobu Arikawa
(Insituteof Laser Engineering Osaka University)
24/10/2018, 08:30
Here we report a novel design of a heating laser for the fast ignition, combining fundamental and second harmonics lights. Such a two-colors laser is expected to heat a dense core more efficiently than a laser only with a fundamental light. We chose a LBO (LiB3O5) crystal which can convert a focusing beam due to its large acceptance of phase matching angle. We experimentally demonstrated the...
Prof.
Shinsuke Fujioka
(Institute of Laser Engineering, Osaka University)
24/10/2018, 08:50
The quest for the inertial confinement fusion (ICF) ignition is a grand challenge, as exemplified by extraordinary large laser facilities like National Ignition Facility (NIF) [J. Lindl et al., Phys. Plasmas 11, 339 (2004), J. Lindl et al., Phys. Plasmas 21, 020501 (2014)]. Although scientific break-even, the energy released by fusion reaction exceeds the energy contains in the compressed...
Dr
Ray Leeper
(Los Alamos National Lab)
24/10/2018, 09:10
The baseline approach to high gain ICF involves the implosion of capsules containing a layer of DT ice [1]. DT ice layer designs require a high convergence ratio (CR > 30) implosion, with a hot spot that is dynamically created from DT mass originally residing in a thin layer at the inner DT ice surface. Although high CR is desirable in an idealized 1D sense, it amplifies the deleterious...
Prof.
Jose Manuel Perlado
(Instituto Fusion Nuclear / Universidad Politécnica Madrid)
24/10/2018, 09:30
Different Inertial Fusion Energy (IFE) First Wall (FW) protections have been proposed in diverse conceptual designs that lead to very different irradiation conditions and macroscopic effects. A review is needed to understand their behavior. Some years ago a European proposal projected the possibility of non-protective FWs considering W and nano-tungsten. This work is describing in detail the...
Dr
Akifumi Iwamoto
(National Institute for Fusion Science)
24/10/2018, 09:50
We study fuel layering for Fast Ignition Realization Experiment (FIREX) cryogenic targets according to two strategies: a foam shell and Infrared (IR) heating. Foam is a porous material and would soak up a liquid fuel uniformly by capillarity. The method has the difficulty to form void-less solid fuel because of the density difference between the liquid and solid phases. We have demonstrated...
Dr
Elena de la Luna
(CIEMAT)
24/10/2018, 10:45
An important aspect of ITER operation will be the termination of the high confinement H-mode phase ($I_p$ ramp-down phase) in a controlled and safe way. Previous ramp-down studies in JET and other devices focused on aspects related to flux consumption and vertical stability control. In this work the emphasis is on aspects related to W accumulation and its control, which can be particularly...
Dr
Tim Happel
(Max-Planck-Institut für Plasmaphysik)
24/10/2018, 11:25
The I-mode is an improved confinement regime of tokamak plasmas where an edge transport barrier is observed only in the heat transport but not in the particle transport. This is in contrast to H-mode confinement, which is characterized by transport barriers for both heat and particles. The I-mode does not exhibit any edge localizes modes. Since the particle confinement is low, the I-mode does...
Dr
Philip Snyder
(General Atomics)
24/10/2018, 11:45
The “Super H-mode” regime is predicted to enable pedestal height and fusion performance substantially higher than for standard H-mode operation. This regime exists due to a bifurcation of the pedestal pressure, as a function of density, that occurs in strongly shaped plasmas above a critical density. Experiments on Alcator C-Mod and DIII-D have achieved access to the Super H-Mode regime, and...
Dr
BENOIT LABIT
(Swiss Plasma Center (SPC) EPFL SWITZERLAND)
24/10/2018, 12:05
A series of experiments has been conducted at AUG and TCV to disentangle the role of fueling, plasma triangularity and closeness to a double null (DN) configuration for the onset of the small ELM regime. At AUG, the role of the SOL density has been revisited. Indeed, it turns out that a large density SOL is not a sufficient condition to achieve the type-II (small) ELM regime. This has been...
Dr
Shwetang Pandya
(India Institute for Plasma Research, Bhat, Gandhinagar, 382-428, India)
24/10/2018, 14:00
Poster
In recent years, the studies of Runaway Electron (RE) generation and energy dynamics in tokamaks have gained great importance from the theoretical and experimental perspective. The generation of high power RE beam during the plasma disruption may damage in-vessel components. Therefore, it is important to study and to suppress the REs for the safe operation of the large size tokamaks, such as...
Mr
Kumar Ajay
(IPR)
24/10/2018, 14:00
Poster
Core-ion temperature measurements are routinely carried out by the energy analysis of passive Charge Exchange (CX) neutrals escaping out of the ADITYA-tokamak (Minor radius a=25 cm, major radius R=75 cm) plasma using a 45-degree parallel plate electrostatic energy analyzer [1]. The temporal evolutions of peak ion temperature in the core regime [typically 80 eV to 120 eV for Aditya circular...
Tim Happel
(Max-Planck-Institut für Plasmaphysik)
24/10/2018, 14:00
Poster
Mr
Amit Kumar Singh
(ITER-India, Institute for Plasma Research)
24/10/2018, 14:00
Poster
In superconducting tokamaks, electric field generated by the central solenoid (CS) for plasma start-up is generally less than that for non-superconducting tokamaks due to the requirement of a robust vacuum vessel and cryostat without insulating break. Moreover, with the CS made of NbTi conductor, there is limitation to maximum dI/dt in the coil to avoid stress limits, resulting in limited loop...
Prof.
Evgenii Gusakov
(Ioffe Institute)
24/10/2018, 14:00
Poster
The extraordinary pump wave two-plasmon decay instability TPDI is analyzed under conditions when only one of the parametrically driven upper hybrid (UH) waves is trapped in the vicinity of the density profile local maximum. It is shown that under these conditions the excitation of absolute TPDI is possible due to a finite width of the microwave pump beam. Its threshold and growth rate are...
Mr
Satyaprasad Akkireddy
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a nuclear fusion reactor, hot and dense D-T plasma is confined using a combination of magnetic fields in a toroidal shaped vacuum vessel. Interaction of this plasma with the wall materials of vacuum vessel is one of the very important areas of interest as plasma-wall interactions will decide the operational life-time of the reactor in terms of plasma as well as material stability. The...
Dr
Taina Kurki-Suonio
(Aalto University)
24/10/2018, 14:00
Poster
The ITER Pre-Fusion Power Operating (PFPO) phase will include half-field/half-current (2.65T, 7.5 MA) and one-third field (1.8T, 5MA) operating scenarios, which ought to allow H-mode access even with limited heating [1].
While PFPO-1 relies only on ECRH and ICRH to achieve the H-mode, in PFPO-2 also the neutral beams will be applied. In the PFPO phases, the plasma will consist of either...
Mr
Abhishek Sinha
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a tokamak electron cyclotron emission (ECE) is measured to determine electron temperature profile and its evolution. Michelson interferometer (MI) diagnostic is capable of measuring the spectrum of the ECE in a wide spectral range (70-500 GHz). Usually MI is calibrated with hot-cold technique. The lab calibration of the MI diagnostics is carried out locally with room temperature and cold...
Mr
Pankaj Kumar Srivastava
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Microwave interferometer diagnostic is designed and installed for carrying out chord averaged density measurements for plasma density between $ \sim 5\times 10^{10}-6\times 10^ {11} cm^{-3}$ respectively in the Source and Target plasma regions of Large Volume Plasma Device (LVPD). These regions are developed in LVPD by the introduction of large Electron Energy Filter (EEF). This helped in...
Mr
Gaurav Shukla
(Pandit Deendayal Petroleum University)
24/10/2018, 14:00
Poster
Plasma rotation and its shear in the edge and scrape-off-layer (SOL) region plays an important role in determining overall confinement of tokamak plasmas. The sources of spontaneous generation of these rotations are still not fully understood. Furthermore, to answer the questions like whether they modify the electric field profile or electric field profile modifies the rotation and its shear,...
Dr
Akifumi Iwamoto
(National Institute for Fusion Science)
24/10/2018, 14:00
Poster
Mr
Umesh Kumar Nagora
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a tokamak, an interferometer system measures plasma density using an electromagnetic wave which experiences a phase shift with respect to a reference signal while passing through the plasma column. In millimetre wave spectrum, usually homodyne and heterodyne systems are used to determine phase information. One of the limitations of the homodyne scheme was its inability to differentiate the...
639.
Design and development of Passive Charge Exchange Neutral Particle Analyzer for ADIYA-U Tokamak
Dr
Snehlata Aggarwal
(institute for plasma research)
24/10/2018, 14:00
Poster
Passive charge exchange diagnostic is well established technique for measuring core-ion temperature of tokamak plasma. Energetic neutral particles that are formed due to charge exchange of plasma ions with neutral atoms, can escape from the plasma. These neutral atoms that are re-ionized and analyzed using analyzer can provide information about the energy distribution of plasma ions [1].
A...
Mr
Jagabandhu Kumar
(InIPR)
24/10/2018, 14:00
Poster
A new passive active multijunction antenna (PAM) has been designed and is in advance stages of fabrication for ADITYA-U tokamak. The PAM antenna has the ability to couple lower hybrid waves (LHW’s) in to the plasmas near cut-off densities. The coupling of LHW’s depends on plasma density and its profile near the mouth of the antenna. To determine these plasma parameters, experimentally, an...
Dr
Payal Pandit
(Institute for Plasma Research, Gandhinagar)
24/10/2018, 14:00
Poster
The hydrogen line series is a sensitive diagnostic of detached divertor. Divertor plasma is characterized by low temperature (1-10 eV) and high density (1019~1020 m-3). The three body recombination dominates the divertor region and is highly sensitive to the divertor plasma Te and ne. Based on earlier experiments, NIR (800 nm-2300 nm) spectroscopy system is designed for Aditya-U tokamak since...
Mr
Jayesh Raval
(Institute for Plasma Research (IPR), Bhat, Gandhinagar, India)
24/10/2018, 14:00
Poster
Study of soft x-ray(SXR) radiation emitted during plasma discharge gives valuable informations on magneto hydrodynamic(MHD) activities, e.g. nature of minor and major disruptions, mode structure, magnetic island, plasma shape, plasma position and chord average electron temperature in tokomak. Intensity of SXR radiation depends mainly on electron temperature, plasma density as well as on...
Prof.
Yoshitaka Mori
(The Graduate School for the Creation of New Photonics Industries)
24/10/2018, 14:00
A laser-driven inertial fusion energy (IFE) reactor should achieve the fusion of injected fuel pellets, which are continuously delivered into the reaction chamber and engaged by laser beams at 10’s Hz. Using a repetitive, 100-fs ultra-intense laser HAMA[1], we have demonstrated the engagement of 1-Hz-injected flying pellets involving fusion neutron reaction for the first time[2]. To induce the...
Dr
Pavel Aleynikov
(Max-Planck-Institut für Plasmaphysik)
24/10/2018, 14:00
Poster
Electron Cyclotron Resonance Heating (ECRH) is the main plasma heating mechanism in Wendelstein 7-X (W7-X) Stellarator. It is provided by 10 gyrotrons at 140 GHz (corresponding to the second harmonic cyclotron resonance at 2.5 T) with the power of 1 MW each. The X- and the O-modes were successfully used in a wide range of operation scenarios: X-mode for low and moderate densities (up to the...
Mr
Tanmay Macwan
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Current distribution inside the tokamak needs to be known for understanding of magnetohydrodynamic (MHD) stability and transport. However, the measurement of radial profile of current density is not easy. The external magnetic measurements yield only the plasma shape and global current profile parameters such as βp and li in tokamaks. The radial current density profile is reconstructed using...
Mr
Lavkesh Lachhvani
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Geodesic Acoustic modes (GAMs), believed to play an important role in L to H transition in tokamaks, are the high frequency branch of the zonal flows and are characterized by toroidally and poloidally symmetric in potential $\phi$ (n=0, m=0) and toroidally symmetric but poloidally asymmetric in density perturbation (n =0, m=1). The coherent modes in the spectral analysis of floating potential...
Ms
Nandini Yadav
(Gujarat University)
24/10/2018, 14:00
Poster
The fuel gas injection(s) in measured quantity during the current flat-top region of Aditya-U tokamak discharges has been observed to modify significantly the edge and scape-off-layer (SOL) plasma properties. The effect of these gas puffs on the neutral temperature and their penetration in the edge and SOL region has been studied by measuring the Hydrogen balmer-emission spectra at 656.28...
Dr
Natsumi Iwata
(Institute of Laser Engineering, Osaka University)
24/10/2018, 14:00
Laser light with relativistic intensities and pulse length exceeding picosecond (ps) has been available recently. Fast electrons generated by over-ps laser-matter interactions are found to be enhanced beyond the scaling laws used in the sub-ps regime. Theories for sub-ps interactions cannot be scaled up simply to ps regime due to that meso-scale physics such as ion fluid dynamics and multiple...
Dr
LALIT AWASTHI
(IPR)
24/10/2018, 14:00
Poster
Understanding electron transport across magnetic field lines in a fusion device is critical. Linear calculations based on numerical and theoretical models reveal that the ETG mode, which is responsible for the turbulence, is a fast growing instability driven by $\nabla T_e$ with growth rate $\gamma_{ETG}\approx\omega_{*T_e}=k_y\rho_e(c_e/L_{T_e})$, when $\eta_e=L_n/L_T$ exceeds a threshold...
Prof.
Gamal Elaragi
(Egyptian Atomic Energy, Cairo, Egypt)
24/10/2018, 14:00
In this paper, Egyptian first inertial electrostatic confinement fusion (IECF) device, constructed at the Egyptian Atomic Energy Authority (EAEA-IEC), is introduced the characterization of IEC Plasma Device. It consists of 2.8 cm stainless steel cathode, 6.5 cm anode diameter with 10 cm diameter 30 cm height vacuum chamber. The discharge current and voltage of plasma discharge has been...
Mr
Jay Joshi
(Institute for Plasma Research, India)
24/10/2018, 14:00
Poster
Capacitive discharges are created in the near field regions of ICRF antennas and thus power coupling by these antennas depend on the sheaths around them. Magnetization of ions in the plasma around these antennas also affects the power coupling into the plasma with major implications in ICRF antenna’s in tokomaks.
A capacitive discharge is designed to study power coupling in such plasmas in a...
Dr
Kishore Mishra
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In ADITYA tokamak, ICRF plasma is produced by a single strap poloidal antenna located at LFS by exciting 24.8 MHz with a RF power < 80 kW for the purpose of developing Ion Cyclotron Wall Conditioning (ICWC) scenarios. Suitable combination of density (by regulating RF power and fill pressure) and Bt are investigated to allow the Fast Wave (FW) propagation in the torus volume. Initially at high...
Mr
Narendra Patel
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In Tokamak, the “gas fuelling control” plays an important role to produce plasma in different operation phases from plasma current initiation till end. Apart from main gas injection for plasma initiation, several plasma parameters such as density, temperature, and events like recycling, disruption / runaway mitigation etc. are controlled by injecting the fuel gas in different amount and from...
Dr
Animesh Kuley
(Indian Institute of Science Bangalore)
24/10/2018, 14:00
Poster
We report on nonlinear PIC simulations of wave-wave and wave particle phenomena relevant for RF heating and current drive schemes in tokamaks. For this we have developed a new nonlinear kinetic simulation model based on the global toroidal code GTC. In this model, the ions are considered as fully kinetic particles obeying the Vlasov equation and the electrons are treated as guiding centers...
Dr
Philip B. Snyder
(General Atomics)
24/10/2018, 14:00
Poster
Dr
Elena de la Luna
(CIEMAT)
24/10/2018, 14:00
Poster
Mrs
RANJANA MANCHANDA
(INSTITUTE FOR PLASMA RESEARCH)
24/10/2018, 14:00
Poster
R. Manchanda1, M. B. Chowdhuri1, Nandini Yadava2, J. Ghosh1, 3, S. Banerjee1, Nilam Nimavat, K. Tahiliani, M. V. Gopalakrishna, U. C. Nagora1, P. K. Atrey1, J. Raval1, Y. S. Joisa1,
K. A. Jadeja1, R. L. Tanna1, and Aditya team
1Institute for Plasma Research, Bhat, Gandhinagar 382 428, India
2Gujarat University, Navrangpura, Ahmedabad 380 009, India
3Homi Bhabha National...
Prof.
Xianzu Gong
(Insititute of Plasma Physics, Chinese Academy Sciences)
24/10/2018, 14:00
Recent EAST experiment has successfully demonstrated long-pulse steady-state scenario with a good plasma performance through the integrated operation since the last IAEA in 2016. A discharge with a duration over 100s has been obtained with multi-RF power heating and current drive. Plasma parameters are as follows, plasma current Ip=0.4 MA, poloidal βP ~1.2, toroidal magnetic field BT=2.5 T,...
Ms
Rachana Rajpal
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
The first phase operations of Aditya-U successfully performed various plasma experiments with repeatable plasma discharges of maximum plasma current of ~160 kA and discharge duration ~250 ms. The electronics and instrumentation requirement for these experiments are mainly of signal conditioning, embedded digital signal processing and automation. The signal conditioning electronics is...
Dr
Khaled Al-Shboul
(Nuclear Engineering Department, Jordan University of Science & Technology)
24/10/2018, 14:00
Future inertial fusion reactors are supposed to work with long pulses or with high repetition rates using repeated pellet implosions. In such extreme environments, the reactor wall materials will be disclosed to short X-ray pulses and fusion generated fragments. This will cause ablation to the wall material in the form of plasma that is expected to collide with each other in the center of the...
Mr
Amulya Kumar Sanyasi
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Whistler waves are driven unstable by the runaway electrons generated in tokamak disruptions with serious consequences on reactor scale tokamaks and by relativistic electrons in space plasmas but with different electron distributions. In LVPD, we report observations on whistlers of Quasi Longitudinal (QL) nature. These are highly oblique in nature and have free energy source asssociated with ...
Mr
Janmejay Umeshbhai Buch
(Institute for Plasma Research), Dr
Surya Kumar Pathak
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
The determination of electron density and its fluctuations are essential in understanding the physical principles that determine the confinement in tokamaks. Aditya tokamak at IPR is routinely operated with a peak density of ~ 3 x 1019 m-3 and a typical magnetic field of 0.75T. We present and describe the bench test calibration and its results and the designed FMCW Reflectometer which is...
Dr
Ray Leeper
24/10/2018, 14:00
Poster
Mrs
sapna Mishra
(ITER-India,Institute for plasma research)
24/10/2018, 14:00
Poster
The investigation of impurities and its transport study in tokomak plasma play a vital role in determining the overall plasma performance. It is important to understand the transport of impurities in tokamak plasmas in order to control impurity inside the plasma and its deleterious consequences affecting overall plasma performance. In Aditya, strong boron like carbon lines are usually seen in...
Prof.
Boris Kuteev
(National Reserch Center Kurchatov Institute)
24/10/2018, 14:00
A vital goal of inertial fusion energy (IFE) research is development of high-precision, mass production technologies for cryogenic fuel targets fabrication and their delivery to the reaction chamber at a high rate (10-20 Hz) [1].
At the Lebedev Physical Institute (LPI), a mechanical mockup of IFE reactor has been proposed [2] for developing the reactor-scaled technologies that are...
Dr
JYOTI ATUL
(INSTITUTE FOR PLASMA RESEARCH, GANDHINAGAR, INDIA)
24/10/2018, 14:00
Poster
Mode conversion (MC) process proves to be of prime importance in fusion as well as in magnetospheric plasma [1,2,3]. However, the presence of multiple ion species, even with small concentrations, can lead to the appearance of new and modified resonance, cutoff, and crossover frequencies [4]. Nonlinear effects such as pump self induced filamentation and parametric decays further complicate the...
Mr
Pavel Minashin
(NRC "Kurchatov Institute")
24/10/2018, 14:00
Poster
The T-15-MD tokamak is planned as a normal magnetic-coil tokamak with a flexible ITER-like configuration of the poloidal magnetic field. The main goal of the tokamak T-15-MD is the achievement of long pulse, non-inductive current drive regimes for a high-aspect-ratio divertor plasma configurations.
The simulations of the ECRH and ECCD in T-15-MD tokamak are carried out with the ray-tracing...
Dr
Malay Bikas Chowdhuri
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Neon impurity injection into the tokamak plasma has been found to improve the plasma confinement, known as Radiative Improved (RI) mode in many tokamaks. It is believed that improved confinement in the RI mode is mostly based on the reduction of growth characteristics of the toroidal ion temperature gradient (ITG) mode due to the increase of Zeff and also because of the suppression of...
Ms
KAJAL SHAH
(PANDIT DEENDAYAL PETROLEUM UNIVERSITY)
24/10/2018, 14:00
Poster
A soft X-ray Crystal spectrometer has been developed to measure toroidal rotation velocity and ion temperature in the core of ADITYA-U Tokamak [1, 2] using Doppler shift and Doppler broadening of helium like argon emission in the x-ray region respectively. The spectrometer uses cylindrically bent Si (111) crystal and two dimension CCD detector to measure resonance spectral line of Ar XVII (1S2...
Dr
Shunsuke Usami
(National Institute for Fusion Science)
24/10/2018, 14:00
Poster
The merging of spherical tokamaks (STs) attract the attention as a candidate of future fusion reactors. In plasma merging experiments of STs, through magnetic reconnection, two torus plasmas are merged into a single torus plasmas with higher beta. In experiments, it is reported that electrons are significantly heated in the vicinity of the X-point, while ions are mainly heated in the...
Mr
Suman Aich
(Scientific officer C)
24/10/2018, 14:00
Poster
In a tokamak, for real-time control of plasma column movement, both horizontal and vertical, accurate measurements of plasma column location is compulsory. Magnetic pick-up coils, measuring induced voltage due to change in flux–linkage to them, are widely used of the measurement of temporal evolution of plasma column position in a tokamak. Although measurements of induced voltages are...
Ms
Abha Kanik
(Research Scholar)
24/10/2018, 14:00
Poster
Laser Heated Emissive Probes (LHEP) have several advantages over conventional filament emissive probes and serve as a tool for direct measurement of plasma potential. Measurement of plasma potential or Electric fields component perpendicular to magnetic field are necessary for fundamental understanding of plasma parameters, transport mechanisms, space charge distribution in plasmas. Owing to...
Dr
BENOIT LABIT
(Swiss Plasma Center (SPC) EPFL SWITZERLAND)
24/10/2018, 14:00
Poster
Dr
Shinsuke Fujioka
(Institute of Laser Engineering, Osaka University)
24/10/2018, 14:00
Poster
Prof.
Dimitri Batani
(Université de Bordeaux)
24/10/2018, 14:00
Poster
Dr
Takeshi Watari
(Central Research Laboratory, Hamamatsu Photonics K.K.)
24/10/2018, 14:00
In the most recent study of inertial confinement fusion, the integration experiments to demonstrate ignition burn are planned using kilojoule to megajoule class laser beam lines in the world. These experiments are based on the “single-shot” experiment of which repetition rate is several-shots per day due to limitations of laser cooling time. A dozen shots every second are required to realize...
Mrs
Kumudni Tahiliani
(Institute for Plasma Research, India)
24/10/2018, 14:00
Poster
Understanding the density limit in a tokamak is very crucial for projecting the fusion grade tokamak machine. An important role in the disruptions for density limit is played by magneto-hydrodynamic (MHD) instabilities associated with the steepening of the current density profile due to the current channel contraction. This shrinkage in the current channel due to increasing densities is...
Dr
Santanu Banerjee
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In fusion devices, runaway electrons (REs) with energies >=10 MeV, generated predominantly during plasma disruptions, can penetrate through the low-Z first wall and melt the interface of actively cooled parts. Majority of disruptions display MHD modes, as precursors. Radiation cool-off at the edge is seen to trigger abrupt growth of MHD modes, mode locking and thereby disruptions. The REs are...
Mr
Tianyang XIa
(Institute of Plasma Physics, Chinese Academy of Sciences)
24/10/2018, 14:00
Poster
In order to understand and control the heat flux issue for the future tokamaks, the particle and heat fluxes of the EAST RF heating H-mode have been simulated by the 6-field 2-fluid model in BOUT++ framework [1]. The simulated particle fluxes induced by the edge coherent turbulence on the outer divertor targets are comparable with the measurements of the width and peak amplitudes by the...
Mr
Sharvil Patel
(Birla Institute of Technology, Jaipur Campus , India)
24/10/2018, 14:00
Poster
Studies of medium and high Z impurities behavior in high temperature tokamak plasmas have become important considering molybdenum, tungsten are being considered as the first wall materials due to its high melting points and capabilities to handle high heat load. These impurity ions are present due to mainly sputtering processes involving plasma facing components in contact with the edge...
Mr
Hideo Nagatomo
(Osaka University)
24/10/2018, 14:00
In the fast ignition of laser fusion, a reliable target design is required for an ignition scale target. This paper shows the first optimized target design of an implosion phase of the fast ignition, which is scalable to larger targets.
The fast ignition scheme can be divided into three processes mainly; the formation of highly compressed fuel core plasma, the generation of high-energy...
Dr
Nicola Bertelli
(Princeton Plasma Physics Laboratory)
24/10/2018, 14:00
Poster
The main goal of the NSTX-U is to operate at B=1T. With this magnetic field, the 1st and 2nd harmonics of hydrogen (H) are located at the high-field side and in the core plasma, respectively. As a consequence, part of the high-harmonic fast-wave (HHFW) injected power can be absorbed by the H population. This condition might open up new HHFW scenarios, which in turn can be relevant for the...
Dr
Abhay Ram
(Massachusetts Institute of Technology)
24/10/2018, 14:00
Poster
The practical and economic viability of tokamak fusion reactors depends, in a significant way, on the efficiency of radio frequency (RF) waves to deliver energy and momentum to the plasma in the core of the reactor. Among the various attributes of RF waves is their ability to heat magnetically confined plasmas, induce plasma currents in an effort to achieve steady state, and modify the current...
Dr
Yasunobu Arikawa
24/10/2018, 14:00
Poster
Dr
Darin Ernst
(MIT)
24/10/2018, 14:00
Poster
Dr
Francesca Turco
(Columbia University)
24/10/2018, 14:40
DIII-D experiments have demonstrated the expansion of the high-betaN hybrid scenario to the high density levels necessary for radiating divertor operation, leading to pedestal enhancement, and showed how the choice of injected impurity impacts the effectiveness of a radiating mantle solution, as well as the impurity transport to the core and the divertor. The scenario was made robust to...
Dr
Golo Fuchert
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
24/10/2018, 15:20
As the first comprehensively optimized stellarator, Wendelstein 7-X (W7-X) is an essential experiment to study high density operation in this kind of device. This contribution presents first experiments on the density dependence of the energy confinement in W7-X and limitations of the achievable density. Theoretical predictions and empirical scaling laws for the energy confinement time in...
Dr
Luca Garzotti
(United Kingdom Atomic Energy Agency - Culham Centre for Fusion Energy)
24/10/2018, 15:40
The JET exploitation plan foresees D-T operations in 2019-20. With respect to the first D-T campaign in 1998, when JET was equipped with a C wall, the experiments will be conducted in presence of a Be-W ITER-like wall and will benefit from an extended and improved set of diagnostics and higher available additional power.
Among the challenges presented by operations with the new wall there are...
Dr
Seung-Hoe Ku
(Princeton Plasma Physics Laboratory)
24/10/2018, 16:40
Despite over 30 years of routine H-mode operation in all the major tokamaks, there has not been a fundamental understanding at the kinetic level on how the H-mode turbulence bifurcation occurs. This is a concern over ITER’s achievability of the H-mode operation with available heating power when the ∇𝑝-driven neoclassical ExB shearing rate is expected to be weak due to smallness of ρ*=ρi/a. The...
Dr
Jon Hillesheim
(Culham Centre for Fusion Energy)
24/10/2018, 17:00
Unraveling the conditions that permit access to H-mode continues to be an unresolved physics issue for tokamaks, and accurate extrapolations are important for planning ITER operations and DEMO design constraints. Experiments have been performed in JET, with the ITER-like W/Be wall, to increase the confidence of predictions for the L-H transition power threshold in ITER. These studies have...
Dr
Lothar Schmitz
(University of California-Los Angeles)
24/10/2018, 17:20
Quantitative proof is presented that the ion polarization current [1] dominates the evolution of the radial electric field E_r across the L-H transition, and needs to be properly taken into account in Ohm’s law. This is an important step towards developing a physics-based reduced L-H transition model, which in addition needs to include at a minimum the poloidal momentum balance, and evolution...
Dr
Mike Kotschenreuther
(Institute for Fusion Studies)
24/10/2018, 17:40
Major progress has been made in understanding the pedestal transport in several areas. 1) For the first time, the instabilities that dominate energy transport in present experimental pedestals are determined, using identifying ratios of the transport they produce in different channels - their “transport fingerprint”. These are derived from the drift kinetic equation for pedestal parameters,...
Dr
Joseph McClenaghan
(Oak Ridge Associated Universities)
24/10/2018, 18:00
Shafranov shift stabilizes turbulence and creates a bifurcation in kinetic ballooning mode(KBM) transport that enables high performance ITB plasmas to be sustained at reactor relevant $q_{95}$. On DIII-D, the internal transport barrier (ITB), high $\beta_N$ ~3, and very high normalized confinement $H_{98,y2}$~1.6 of the high $\beta_p$ scenario has been achieved at $q_{95}$~6.5. This is...
Dr
Seung-Hoe Ku
(Princeton Plasma Physics Laboratory)
25/10/2018, 08:30
Poster
Dr
paolo zanca
(consorzio rfx)
25/10/2018, 08:30
Poster
A density limit (DL), causing either a disruption or a soft termination of the discharge, is generally found in magnetic confinement fusion devices. Some empirical scaling laws have been proposed to order the maximum achievable densities. The Sudo density, n_Sudo∝(P〖 B〗_ϕ )^0.5 [1], with P the heating power, is generally applied to the stellarator. The Greenwald density, n_G=I_p⁄((π a^2 ) )...
Mrs
Deepti sharma
(Institute for Plasma Research, Gandhingar, India)
25/10/2018, 08:30
Poster
The ADITYA tokamak device is used to produce circular plasma for few
hundreds of milli-seconds. The edge physics study in this device is led to
significant contributions. The upgradation of this device is focused to
address issues relevant to heat removal capability at the plasma edge. This
requires to construct plasma equilibrium with divertor configuration. In this regard, additional...
Dr
G.Z. Hao
(Southwestern Institute of Physics, Chengdu 610041, China)
25/10/2018, 08:30
Poster
There is a longstanding issue on the physical nature of a low frequency (<50 kHz) MHD instability observed at the early phase of the discharges of a spherical tokamak (ST) - the National Spherical Torus Experiment (NSTX) (Ono et al 2000 Nucl. Fusion 40 557). This work provides evidence that low frequency modes in spherical tokamaks are often driven by the rapid plasma flow. The centrifugal...
Dr
Wenzhe Mao
(University of Science and Technology of China)
25/10/2018, 08:30
Poster
Electrostatic turbulence is the main constrain of confinement improvement on low $\beta$ toroidal magnetic confinement devices. With the development of high $\beta$ operation scenario, electromagnetic turbulence is expected to become important for development of resistive tearing mode and resistive wall mode. The characteristics of electromagnetic turbulence on KTX are studied in low current...
Dr
Gunyoung Park
(National Fusion Research Institute)
25/10/2018, 08:30
Poster
Control of the edge localized modes (ELMs) is one of the most critical issues for a ITER and the future tokamak fusion reactors. In order to develop a *predictive* model of the access to ELM-crash suppressed states, it is essential to understand first the underlying physics mechanism of ELM-crash-suppression. This paper reports comparative simulation results for particular KSTAR experimental...
Dr
Tuomas Tala
(VTT, Association Euratom-Tekes)
25/10/2018, 08:30
Poster
Prof.
Giuseppe Calabro
(University of Tuscia)
25/10/2018, 08:30
Poster
Prof.
YI LIU
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
Advanced tokamak scenario with central q close to 1 has been achieved on HL-2A tokamak. An ITB has been observed during the nonlinear evolution of a saturated long-lived internal mode (LLM) or fishbone activities in HL-2A discharges as the q-profile formed a very broad low-shear region with qmin ~ 1. Such steep ion temperature-gradient zone locates around r/a=0.5-0.6 with Ti>Te. The observed...
Mr
Leonid Khimchenko
(ITERRu)
25/10/2018, 08:30
Poster
Extreme high heat loads, both during steady state and transient events, expected on the tungsten divertor plates of the ITER facility, undertaken at Cadarache, France. In this paper nonambipolar plasma flow toward the surface, due to arcs and sparks, was investigated as mechanism of power exhaust, leading to enhanced heating of plasma facing materials (PFMs) at a very high heat load. This...
Dr
Yipo Zhang
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
Effect of the pedestal deposited impurity on the edge-localized mode (ELM) behaviour has been observed and intensively investigated in the HL-2A tokamak. Impurities have been externally seeded by a newly developed laser blow-off (LBO) system. Both mitigation and suppression of ELMs have been realized by LBO-seeded impurity. Measurements have shown that the LBO-seeded impurity particles are...
Dr
Juhyung Kim
(National Fusion Research Institute)
25/10/2018, 08:30
Poster
Edge localized modes (ELMs) are quasi-periodic relaxation of tokamak pedestal, releasing large heat flux on divertor places. Although ELMs are thought to be triggered by MHD peeling-ballooning instability, the nonlinear relaxation process is not fully understood.
MHD filaments can carry out heat to scrape of layers (SOL) without reconnection [1].
On the contrary, a magnetic topology change...
Dr
Alexander Melnikov
(NRC 'Kurchatov Institute')
25/10/2018, 08:30
Poster
New experimental observations and theoretical description of the plasma potential and radial electric field Er formation in the T-10 tokamak are presented. The potential was measured by heavy ion beam probe (HIBP) diagnostic from the plasma core to edge with high spatial (<1 cm) and temporal (1 mus) resolution, and by Langmuir probe (LP) at the edge. Low-density OH deuterium plasma...
Ms
Y Patil
(Institute For Plasma Research)
25/10/2018, 08:30
Poster
The APPEL (Applied Plasma Physics Experiments in Linear Device) is an experimental system designed to carry out basic plasma physics experiments as well as serve as a test-bed for experimenting various plasma facings components interaction with strongly magnetized plasma. This versatile device consists of 16 large electromagnet coils weighing up to 700 kg each, which are made from CTC...
Mr
Peiwan Shi
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
The stationary and nonstationary toroidal Alfvén eigenmodes (TAE) driven by energetic-ion have been observed on HL-2A. The mode frequencies are about 90-200 kHz and toroidal mode numbers for the most unstable mode are n=1–3. The radial structure of the mode with n=2 confirmed by the Alfvén Mode Code (AMC) make up of poloidal harmonic m=2 and m=3, which is a typical feature of TAE. The...
Allan Reiman
(Princeton Plasma Physics Lab)
25/10/2018, 08:30
Poster
A small magnetic island has only a small effect on the ambient pressure gradient, so that the pressure is not constant on the flux surfaces in and near the island. The length scale determining which islands may be regarded as “small” in this context is determined by the ratio of perpendicular to parallel transport. We numerically explore the effect of such a small island on the MHD equilibrium...
Prof.
Xianming SONG
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
HL-2M tokamak is now under construction in China as a modification to the HL-2A facility, with nominal parameters as follows: Ip=1.5-3.0MA, B=2.2T, major radius= 1.78m, minor radius=0.65m, elongation =1.6-1.8, triangularity >0.5. It is a real challenge to build a new machine in fusion community, HL-2M suffers from a long delay for the first plasma. In order to fulfil the requirement of...
Dr
Jeronimo Garcia
(CEA IRFM)
25/10/2018, 08:30
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
Predictability of burning plasmas is a key issue for designing and building credible future fusion devices. The integration of several physics aspects is mandatory for an accurate extrapolation from present day plasmas, mainly with deuterium (D) as the main ion species, to conditions in which the ion mixture will be dominated by Deuterium-Tritium (DT).
In this framework, an important effort...
Dr
Mike Kotschenreuther
(Institute for Fusion Studies)
25/10/2018, 08:30
Poster
Dr
Toseo Moritaka
(Institue for Fusion Science)
25/10/2018, 08:30
Poster
We investigate radial electric field structure in Large Helical Device and its impact on high-energy particle loss at the material wall. We employ global gyrokinetic particle-in-cell code for whole-device simulation, X-point Gyrokinetic Code (XGC), which is currently being extended to non-axisymmetric geometries. The whole-device modeling of fusion plasma is needed to understand edge plasma...
Dr
Robert Hager
(Princeton Plasma Physics Laboratory)
25/10/2018, 08:30
Poster
The gyrokinetic neoclassical particle-in-cell code XGCa coupled to the MHD code M3D-C1 is applied to study the particle and heat flux caused by external 3D magnetic perturbations in a DIII-D H-mode plasma. Despite the existence of KAM surfaces in the pedestal, our simulations, which so far are limited to the 0.5 to 1 ms directly after the RMP field is switched on, show the beginning of density...
Dr
Jon Hillesheim
(Culham Centre for Fusion Energy)
25/10/2018, 08:30
Poster
Dr
Golo Fuchert
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
25/10/2018, 08:30
Poster
Mr
Maxim Nurgaliev
(National Research Centre "Kurchatov Institute")
25/10/2018, 08:30
Poster
Investigation of ion heat conductivity in plasma with ECR-heating and suppressed saw-teeth and modes $(m,n)=(1,1)$ and $(2,1)$ is carried out. Off-axis heating (localization radius is $\rho=r/a \approx0.5$) and combined heating (on-axis ECRH together with off-axis) are considered. It is shown for the ohmic stage that ion heat conductivity is on a neoclassical level in the central zone $\rho...
Prof.
Xianzu Gong
(Insititute of Plasma Physics, Chinese Academy Sciences)
25/10/2018, 08:30
Poster
Dr
Francesca Turco
(Columbia University)
25/10/2018, 08:30
Poster
Dr
Masahiko Sato
(National Institute for Fusion Science)
25/10/2018, 08:30
Poster
For the high beta plasmas in the inward shifted Large Helical Device (LHD) configurations, the plasma peripheral region is theoretically MHD unstable region since there is always a magnetic hill in the plasma peripheral region. However, high beta plasmas with about 5% of the volume averaged beta value are stably obtained in the LHD experiments. This implies that the nonlinear saturation level...
Mr
L. Schmitz
(University of California-Los Angeles)
25/10/2018, 08:30
Poster
Min Jiang
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
Magnetic islands formed in magnetically confined plasmas have significant influence on plasma profiles and cross-field transport, and can even cause plasma disruption [1,2]. However, observations of internal transport barriers near the rational magnetic surface suggest the importance of magnetic islands in plasma confinement via increase of flow shear at the island boundary [3,4]. In recent...
Linjin Zheng
(University of Texas at Austin)
25/10/2018, 08:30
Poster
Recently, discharges with negative triangularity were created in the DIII-D tokamak. These discharges exhibited the H-mode-level confinement features with L-mode-like edge behavior without ELMs (M.E. Austin et al., Bull. Am. Phys. Soc. vol. 62 (2017)). This led us to extensively examine the MHD stability of negative triangularity tokamaks. Using the numerically reconstructed experimental...
Dr
Shizuo Inoue
(QST)
25/10/2018, 08:30
Poster
The interaction of a locked tearing mode with a non-axisymmetric control field is found to be in good qualitative agreement with predictions of a nonlinear resistive MHD model [1]. Locked tearing mode islands often lead to disruptions in tokamaks. However, experiments have shown that unlocking and rotation of the island by a rotating control field (CF) can postpone or prevent a disruption [2]....
Dr
Xiaoquan JI
(Southwestern Institute of Physics, Chengdu 610041 China)
25/10/2018, 08:30
Poster
In HL-2A low rotation and relatively low density plasmas, the critical threshold of the intrinsic error field penetration will be decreasing. And the multi-helicity islands can be seeded by the non-axisymmetric error field penetration, and lead to the change of rotation profile, enhanced transport or even disruption. Sheared flow arising from momentum injection can suppressed the coupled...
Dr
FENG LIU
(Université Côte d’Azur)
25/10/2018, 08:30
Poster
Both nonlinear simulations and experiments of DIII-D QH-mode plasmas show that E×B rotation plays an essential role for obtaining the QH-mode. However, the mechanism for the QH-mode onset and its saturation, the influence of other rotation flows such as neoclassical flow, diamagnetic flow as well as the influence of resistive wall still remains unclear due to the complexity of the physics of...
Dr
Daniel López-Bruna
(EsLNF)
25/10/2018, 08:30
Poster
The relaxation of the constraint of periodicity imposed by the external confining magnetic field coils in a nominally 4-field period Helias Advanced Stellarator configuration produces weak periodicity-breaking deformations of the plasma. The corrugations are driven by the interaction of the pressure gradient with the magnetic field line curvature and correspond to saturated ideal...
Prof.
Sibylle Günter
(Max-Planck-Institut für Plasmaphysik)
25/10/2018, 08:30
Poster
Neoclassical tearing modes (NTMs) can degrade plasma confinement or even lead to disruptions in existing tokamak discharges. To understand their triggering mechanism by sawtooth crashes and the effect of error fields or externally applied resonant magnetic perturbations (RMPs) on their onset remain to be important for ITER or a fusion power plant. In this paper these two issues are studied...
Mr
Rupak Mukherjee
(Institute for Plasma Research)
25/10/2018, 08:30
Poster
Rupak Mukherjee, Rajaraman Ganesh
Institute for Plasma Research, HBNI, Gandhinagar, Gujarat, India, 382428.
ganesh@ipr.res.in
Since the advent of Taylor-Woltjer theory [1,2], it has been widely believed that situations with perfectly conducting boundaries and near ideal conditions, the final state of MHD system would be force-free Taylor-Woltjer states defined as curl B = alpha B with...
Dr
Carine Giroud
(CCFE)
25/10/2018, 08:30
Poster
Dmitriy Ryzhakov
(RuKurchatov)
25/10/2018, 08:30
Poster
One of the main goals of researching global plasma disruptions is to find a way to prevent the formation of runaway electron beams, after the plasma current disruption. A possible way to solve this problem is to generation of strong MHD perturbation during current decay. The experimental study of density limit disruption on tokamak T-10, for study dependency a duration of plasma current decay...
Dr
Jun Cheng
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
Streamer, as well as zonal flow is a very challenging subject since it is expected to have significant effects on confinement in high temperature plasmas. Theoretical simulation predicts that streamers originate from the nonlinear development of turbulence driven by electron and ion temperature gradient. In experiments, few works have reported the streamer observation only up to now, and...
Prof.
Yuhong Xu
(Southwest Jiaotong University)
25/10/2018, 08:30
Poster
The Chinese First Quasi-axisymmetric Stellarator (CFQS) is a joint project of international collaboration. It is designed and fabricated by Southwest Jiaotong University (SWJTU) in China and National Institute for Fusion Science (NIFS) in Japan. The target parameters of CFQS are as follows: toroidal periodic number N = 2, major radius R = 1.0 m, aspect ratio R/a = 4.0 and magnetic field...
Dr
Wulyu Zhong
(CnSWIP)
25/10/2018, 08:30
Poster
In HL-2A H-mode plasmas, the confinement and pedestal response to impurity seeding have been recently investigated [1]. It has been observed that a broadband electromagnetic (EM) turbulence can be driven by peaked impurity density profile at the edge plasma region, and governed by double critical gradients of the impurity density [2]. In addition to the spontaneously accumulated impurity, the...
Dr
Rui Coelho
(Instituto de Plasma e Fusão Nuclear / Instituto Superior Técnico)
25/10/2018, 08:30
Poster
The reconstruction of Tokamak plasma equilibrium is a fundamental step in the understanding of fusion plasma physics since it sets the starting point for all subsequent plasma modelling applications and experimental data interpretation. The verification and validation of the numerical codes used to reconstruct plasma equilibrium, using as many available input experimental data e.g. magnetic...
Prof.
A.V. Burdakov
(Budker Institute of Nuclear Physics SB RAS, Novosibirsk, Russia)
25/10/2018, 08:30
Poster
The challenge of creation of an open trap with the reactor-grade plasma is achievable if such trap will use specialized sections of the magnetic system for suppression of particle and energy losses along the magnetic field. Currently, two new experimental devices are under construction in the Budker Institute for studies of physics of plasma confinement in magnetic systems with multiple-mirror...
Dr
Longwen Yan
(Southwestern Institute of Physics)
25/10/2018, 08:30
Poster
The stability and performance of tokamak plasmas are routinely limited by various magneto-hydrodynamic (MHD) instabilities, such as neoclassical tearing modes (NTMs). This paper presents a rather simple method to control the NTMs in real time (RT) on a tokamak, including the control principle of feedback approach for RT suppression and stabilization for the NTMs. The control system combines...
Dr
Leonardo Pigatto
(ItRFX)
25/10/2018, 08:30
Poster
The superconducting tokamak JT-60SA is being built in Naka (Japan) under the Broader
Approach Satellite Tokamak Programme jointly by Europe and Japan, and under the Japanese
national programmme. JT-60SA has an important supporting mission for the development of
fusion energy: designed to achieve long pulses (100 s) and break-even equivalent plasmas,
challenging high $\beta$ operation...
Dr
Yueqiang Liu
(General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA)
25/10/2018, 08:30
Poster
Edge localized modes (ELMs) release large bursts of heat and particle flux to the plasma facing components in tokamaks, potentially causing significant material erosion in future devices such as ITER. Externally applied three-dimensional (3D) resonant magnetic perturbations (RMP) have been experimentally demonstrated to be effective in tailoring these ELM bursts. A significant yet not well...
Zhihong Lin
(UC Irvine)
25/10/2018, 08:30
Poster
Resonant magnetic perturbations (RMPs) can be used to mitigate or fully suppress the harmful Edge Localized Modes (ELMs). In DIII-D, the ELM suppression is observed to be correlated with the enhanced particle and heat transport near the pedestal top. Initial simulations using Gyrokinetic Toroidal Code (GTC) show that the kink responses to the 3D RMP have little effect on the growth rate of...
Mr
Craig Bowie
(Australian National University)
25/10/2018, 08:30
Poster
Sandpile models have been used to provide simple phenomenological models without incorporating the detailed features of a fully featured model. The Chapman sandpile model (Chapman et al *Physical Review Letters* 86, 2814 (2001)) has been used as an analogue for the behaviour of a plasma edge, with mass loss events (MLEs) being used as analogues for (and anagrams of) ELMs. Here we modify the...
Dr
Luca Garzotti
(United Kingdom Atomic Energy Agency - Culham Centre for Fusion Energy)
25/10/2018, 08:30
Poster
Mr
Jervis Mendonca
(Institute for Plasma Research Gandhinagar INDIA)
25/10/2018, 08:30
Poster
The (m=1, n=1) internal kink instability plays an important role in the dynamics of a
tokamak discharge and is responsible for the occurrence of sawtooth oscillations. Many
experimental observations show that plasma rotation can strongly influence the
stability properties of sawtooth oscillations. Past theoretical flow studies to understand such stabilization have been done in the low...
Dr
Vadim Prikhodko
(Budker Institute of Nuclear Physics SB RAS)
25/10/2018, 08:30
Poster
Interest to magnetic mirrors went missing in the 1980's because of three key problems: magnets' complexity, micro-instabilities, and low temperature of plasma. However, researches on the Gas Dynamic Trap (GDT) device at the Budker Institute of Nuclear Physics demonstrates the possibility to overcome these difficulties. Confinement of plasma with high energy density have been performed on GDT...
Dr
Wei Chen
(Southwestern Institute of Physics, P.O. Box 432 Chengdu 610041, China)
25/10/2018, 08:30
Poster
Magneto-hydrodynamic (MHD) instabilities in hot plasmas can strongly limit the operational parameter space of a fusion reactor. Their stabilization, suppression and active control have therefore attracted much attention, in particular with regard to expansion of the operational space, enhancing the fusion performance and decreasing the energetic particle losses in both present-day fusion...
Dr
Matthew John Hole
(Australian National University)
25/10/2018, 08:30
Poster
Edge Localised Modes (ELMs) are thought to be caused by a spectrum of magnetohydrodynamic instabilities, including the ballooning mode. While ballooning modes have been studied extensively both theoretically and experimentally, the focus of the vast majority of this research has been on isotropic plasmas. The prevalence of pressure anisotropy in modern tokamaks thus motivates further study of...
Dr
Gleb Kurskiev
(Ioffe Physical-Technical Institute of the Russian Academy of Sciences)
25/10/2018, 08:30
Poster
The presentation is devoted to the overview of thermal energy confinement time study at the compact spherical tokamak Globus-M. Globus-M has major radius R = 0.35 m and minor radius a = 0.21 m (R/a ~ 1.6). The lower-null magnetic configuration is characterized by moderate elongation k~1.9 and triangularity δ~0.35. The present study was performed in both OH and NBI heated H-mode plasma. The...
Dr
Joseph McClenaghan
(Oak Ridge Associated Universities)
25/10/2018, 08:30
Poster
Prof.
Kenichi Nagaoka
(National Institute for Fusion Science)
25/10/2018, 08:50
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
A remarkable achievement of $T_{\rm i0} = 10$ keV with $Z_{\rm eff} = 2$ was obtained in Large Helical Device (LHD). In order to clarify transport characteristics in ion internal transport barrier (ion ITB) formation with isotope effect, a dataset of pure deuterium (D) ($n_{\rm D}/n_{\rm e} > 0.85$) and pure hydrogen (H) ($n_{\rm H}/n_{\rm e} > 0.85$) plasmas for high-ion-temperature...
Dr
Francis Casson
(CCFE, Culham Science Centre, Abingdon, UK)
25/10/2018, 09:10
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
The evolution of the JET high performance hybrid scenario, including central accumulation of the tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based models. 8 transport channels ($T_i,T_e,n_D,n_{Be},n_{Ni},v_{tor},j$) are modelled predictively with self-consistent predictions for sources, radiation,...
Dr
Nobuhiko Hayashi
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 09:30
PPC - Plasma Overall Performance and Control
Oral
Plasmas and their operation scenarios have been predicted by using integrated modelling codes towards the exploitation of JT-60SA experiment. Through the close collaboration between Japan and EU including the model validation and verification using JT-60U and JET experimental data, the following key results were obtained in various modelling activities. Improved modelling predicted a...
Dr
Colin Chrystal
(General Atomics)
25/10/2018, 09:50
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Toroidal rotation in ITER is predicted with a combination of intrinsic and NBI sources and gyrofluid modeling of momentum transport, and it is found to play a significant role in enhancing D-T fusion performance. In a large tokamak such as ITER, intrinsic sources of rotation as well as rotation drive from applied 3D fields will become more significant due to a relatively low amount of neutral...
Dr
Carlos Paz-Soldan
(General Atomics)
25/10/2018, 10:45
Measurements and modeling of runaway electron (RE) dissipation in DIII-D has resolved key experimental discrepancies and validated predictions for ITER, improving confidence that RE mitigation and avoidance can be predictively optimized without risking first-wall integrity. Energy-resolved measurements of hard X-ray (HXR) flux with a unique gamma-ray imaging (GRI) system demonstrate that...
Dr
Jose Ramon Martin-Solis
(Universidad Carlos III de Madrid)
25/10/2018, 11:05
THS - Magnetic Confinement Theory and Modelling: Stability
Oral
Large amounts of MeV runaway electrons (REs) can be generated during disruptions which pose a serious threat for future large tokamak devices like ITER. Thus, it is an urgent task to develop robust and confident systems for their control and mitigation. The injection of high-Z impurities by MGI or SPI constitute one of the most promising schemes. Here, with the aim of evaluating the...
83.
Self-consistent runaway beam formation in 3D magnetic fields during radiation-driven disruptions
Dr
Akinobu Matsuyama
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 11:25
THS - Magnetic Confinement Theory and Modelling: Stability
Oral
We report new simulations that predict three-dimensional (3D) spatial profiles of runaway electrons (REs) throughout the whole evolution of disruption plasmas using a nonlinear reduced MHD code including a runaway beam model. Both the RE generation mechanisms relevant to mitigated disruption scenario for D-T activation phase in ITER and the convective transport of REs due to disruptive MHD...
Dr
Leopoldo Carbajal
(Oak Ridge National Laboratory)
25/10/2018, 11:45
THS - Magnetic Confinement Theory and Modelling: Stability
Oral
We present the validation of theoretical models for the pitch-angle probability distribution function (PDF) of runaway electrons (RE), through simulations of synchrotron radiation (SR) in DIII-D quiescent [1] and disrupted [2] plasmas for which the energy PDF is known from measurements but the pitch-angle PDF is poorly understood. SR of RE in magnetically confinement fusion plasmas is...
Dr
Henry Strauss
(HRS Fusion)
25/10/2018, 12:05
THS - Magnetic Confinement Theory and Modelling: Stability
Oral
It has been thought that asymmetric vertical displacement event (AVDE) disruptions in
ITER might produce large electromechanical forces on the walls and other conducting structures
surrounding the plasma.
It is shown that ITER
AVDE disruptions
should produce a small
asymmetric wall force, comparable to JET. This is demonstrated in simulations [1,2] with the M3D 3D MHD code...
Dr
Theresa Wilks
(UsMIT)
25/10/2018, 14:00
Poster
Analysis of pedestal characteristics for Quiescent H-mode (QH) and I-mode plasmas from recent experiments on DIII-D and C-Mod exhibit a growing understanding of the access requirements necessary to obtain edge fluctuations or MHD that drive edge particle transport needed to remain ELM-free. In DIII-D QH-mode plasmas, critical values of ExB shear are required in experiment in order to suppress...
Dr
Carlos Paz-Soldan
(General Atomics)
25/10/2018, 14:00
Dr
Michael Bongard
(University of Wisconsin-Madison)
25/10/2018, 14:00
Poster
Robust non-solenoidal startup methods may simplify the cost and complexity of next-step burning plasma devices, and especially STs, by removing the need for a solenoid. Experiments on the $A\sim1$ Pegasus ST are advancing the physics and technology basis of Local Helicity Injection (LHI). LHI creates high-$I_p$ tokamak plasmas without a solenoid by injecting helicity with small current sources...
Dr
Silvana Nowak
(IFP - CNR , Milano, Italy)
25/10/2018, 14:00
Poster
Stability of JET baseline and hybrid scenarios from previous and present experimental campaign is investigated in the framework of the JET1 task on MHD analysis and modeling in support of scenario development. Modeling of Neoclassical Tearing Modes (NTMs) onset and their effect on heavy impurity transport is performed via the European Transport Simulator (ETS), encompassing an NTM module and...
Ms
AMRITA BHATTACHARYA
(INDIAN INSTITUTE OF TECHNOLOGY KANPUR)
25/10/2018, 14:00
Poster
The radial impurity transport equation describes the distribution of impurity ion species with different charge states perpendicular to magnetic surfaces of tokamak plasma. The impurity transport equation for each ion with ionization state Z is a second order, coupled, parabolic partial differential equation described in terms of number densities of charge states Z, Z-1 and Z+1. A...
Dr
Henry Strauss
(HRS Fusion)
25/10/2018, 14:00
Dr
Michael Cole
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
Whole-volume gyrokinetic simulations of stellarators are necessary to address a number of important physics and engineering issues, including energetic particle confinement op- timisation and turbulent transport prediction. In recent work, a whole-volume stellarator version of the global gyrokinetic Particle-In-Cell (PIC) code XGC[1] is under development. A 3D interpolation of equilibrium...
Dr
Michio Okabayashi
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
M. Okabayashi
Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543-0451, USA
mokabaya@pppl.gov
DIII-D experiments on control of locked tearing modes are in good qualitative
agreement with predictions of a non-linear reduced MHD code (AEOLUS-IT) [1].
Robust avoidance of locked tearing modes that may cause disruptions is a prerequisite
for successful ITER...
Mr
Houyang Guo
(General Atomics)
25/10/2018, 14:00
Poster
A Small Angle Slot (SAS) divertor has been installed on the DIII-D tokamak to further evaluate the role of divertor closure in achieving efficient heat dispersal for steady-state tokamaks. Initial experiments have shown a significant reduction of the electron temperature (T_e) across the divertor target and access to dissipative divertor operation at lower H-mode operational densities while...
Prof.
Cary Forest
(University of Wisconsin-Madison)
25/10/2018, 14:00
Poster
Abstract: We report an overview of theoretical and experimental work at the University of Wisconsin leading to a fusion neutron source based on the Gas Dynamic Trap concept. The design considers the implications of several recent physics and technological advances and uses (1) off-the-shelf MRI magnets for an inexpensive central cell, (2) state-of-the-art small and planar high field REBCO...
Dr
John deGrassie
(General Atomics)
25/10/2018, 14:00
Poster
Scaling of intrinsic rotation in DIII-D H-mode plasmas demonstrates a strong correlation with the ion temperature (Ti) and stored plasma thermal energy, indicating a coupling between the turbulent intrinsic momentum flux and the turbulent energy flux [1]. The empirical scaling [1] of intrinsic rotation with plasma stored energy has been recently explored by novel experiments on DIII-D that...
Dr
Steven Sabbagh
(Columbia University)
25/10/2018, 14:00
Poster
Disruption prediction and avoidance is a critical need for next-step tokamaks such as ITER, as disruptions can place significant thermal heat loads and electromagnetic forces on the device and can potentially lead to damage from runaway electrons. Meeting these challenging goals with the high reliability required for ITER and future tokamaks requires multiple approaches, including an...
Mr
B.A. Grierson
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
A novel capability has been added to the DIII-D neutral beam injection system, enabling in-shot variation of beam energy and current for the first time [1]. This new capability is now being explored as a tool for integrated control and optimization of equilibrium profiles and Alfvén eigenmode (AE) activity. The capability provides an alternative to the typically used pulse-width-modulation...
Dr
Nirmal Kumar Bisai
(Institute for Plasma Research, Bhat, Gandhinagar-382428, India)
25/10/2018, 14:00
Poster
High Z Impurity seeding/puffing is an important topic as it is capable to provide radiative improvement of confinement and disruption mitigation in future tokamaks. Here, in this work, numerically and experimentally, we investigate the effect of low density 1% Ne gas (Z = 10, A = 20) seeding and also massive gas puffing. Two dimensional electrostatic interchange turbulence simulation has been...
Dr
Ahmed Diallo
(PPPL)
25/10/2018, 14:00
Poster
Investigations of pedestal evolution between edge-localized-modes (ELMs) in DIII-D provide strong evidence that coupling of modes located near rational surfaces close to the separatrix leads to the onset of an ELM. While the peeling ballooning model is the leading candidate for the ELM phenomenology, the triggering mechanism is not yet understood and remains one of the most outstanding...
Dr
Tobias Görler
(DeMPIPGarc)
25/10/2018, 14:00
Poster
Although remarkable progress in ab initio nonlinear gyrokinetic plasma core turbulence studies has been seen in the last decade, some important open issues remain – e.g., in view of high performance discharges where magnetic fluctuations tend to reduce the turbulence levels and where the presence of fast ions may provide further significant stabilization enhancements. This effect was shown to...
Dr
Edward Hinson
(University of Wisconsin-Madison)
25/10/2018, 14:00
Poster
It is shown for the first time that global exhaust of helium, measured by effective helium particle confinement time (𝛕p,He), is improved during edge localized mode (ELM) suppression by resonant magnetic field perturbations (RMP) in high confinement (H-mode) ITER-shaped tokamak plasmas at DIII-D. An up to 40% reduction of 𝛕p,He during RMP-ELM suppression compared to ELMy H-mode discharges...
Nathaniel Ferraro
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
Results from the 2016 NSTX-U campaign and the subsequent recovery effort have led to significant new insights regarding error fields in the NSTX-U experiment in particular, and in spherical tokamak configurations in general. During the experimental campaign, many L-mode discharges were found to be locked from the q=2 surface outward, indicating the presence of error fields. At the conclusion...
Dr
Jayson Barr
(General Atomics)
25/10/2018, 14:00
Poster
Recent experiments on DIII-D and EAST are developing the techniques and scientific understanding that ITER and future devices will need for safe, low-disruptivity shutdown. ITER needs options for reliable termination both in normal operation as well as in response to an off-normal event, where speed to soft landing is paramount. A large survey of ramp-down techniques in a variety of DIII-D...
Dr
Bart Van Compernolle
(University of California, Los Angeles)
25/10/2018, 14:00
Poster
Recent work on ICRF physics at the Large Plasma Device (LAPD) at UCLA has focused on deleterious near-field antenna effects, such as RF rectification, sputtering, convective cells and power lost to the plasma edge. Plasma parameters in LAPD are similar to the scrape-off layer of current fusion devices. The machine has a 17 m long, 60 cm diameter magnetized plasma column with typical plasma...
Dr
Alberto Loarte
(ITER Organization)
25/10/2018, 14:00
Poster
RMP ELM suppression experiments at ITER-like conditions (shape, collisionality, RMP spectrum) in DIII-D show little splitting of the heat flux to the divertor targets, despite robust splitting in the particle flux. This lack of divertor heat flux splitting is a potentially important result for ITER because splitting of the divertor heat flux into multiple lobes displaced from the primary...
Dr
Jeronimo Garcia
(CEA IRFM)
25/10/2018, 14:00
Prof.
Zhihong Lin
(UsUCALIrv)
25/10/2018, 14:00
Poster
Experimental progress by TAE Technologies has led to successful suppression of MHD instabilities in field-reversed configuration (FRC) plasmas using C-2U and C-2W devices. Resultant particle and energy confinement times are on the order of several milliseconds, governed by micro-turbulence driven transport processes. Understanding these mechanisms is essential towards improved confinement and...
Dr
Daniel López-Bruna
(EsLNF)
25/10/2018, 14:00
Poster
In toroidal magnetic confinement fusion research, one-dimensional (1D) transport models rely on one radial coordinate that labels nested toroidal flux surfaces. The presence of magnetic islands in the magnetic geometry does not impede making 1D transport calculations if the island regions are excluded and then, if necessary, treated separately. In this work we show a simple way to modify the...
Dr
Mario Podesta
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
Global Alfvén eigenmodes (GAE) have been extensively studied on NSTX and with analytic and numerical modeling. Multiple GAE with a range of toroidal mode numbers are commonly observed in NSTX plasmas heated with neutral beams. Recently, analytic and numerical modeling has been used to very successfully model the suppression of GAE experimentally observed with the injection of high pitch (V||/V...
Ms
Emi Narita
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 14:00
Poster
A novel quasilinear particle transport model is constructed by joint analyses with gyrokinetic calculations and JT-60U experimental data. The new model deals with the diagonal (diffusion) and off-diagonal (pinch) transport mechanisms individually. Besides the decomposition, realistic particle sources from neutral-beam fueling are taken into account, which have not been discussed in earlier...
Dr
Max Austin
(UsIFS)
25/10/2018, 14:00
Poster
Discharges with negative triangularity (-delta) shape have been created in DIII-D with H-mode-like confinement (H98y2 = 1.2) and high normalized beta (beta_N = 2.6) with L-mode-like edge pressure profiles and no ELMs. These inner-wall-limited plasmas with delta = -0.4 had the same global performance as a positive triangularity (delta = +0.4) ELMing H-mode discharge with the same I_p,...
Dr
Thomas W. Petrie
(General Atomics)
25/10/2018, 14:00
Poster
Enhanced radiation has been used to reduce divertor heat flux in high power, high performance (AT) double null divertor (DND) and near-DND plasmas in DIII-D, while at the same time maintaining acceptable energy confinement and particle control. Effective radiating mantle operation in high power AT plasma depended strongly on the location of electron cyclotron (EC) heating deposition, on...
Dr
Kathreen Thome
(Oak Ridge Associated Universities)
25/10/2018, 14:00
Poster
Three high-frequency modes observed in the DIII-D tokamak have been identified as energetic particle instabilities driven unstable by anisotropic fast ions and runaway electrons. These modes could serve as control tools of the energetic particle distribution in fusion-relevant plasmas. (1) Whistler waves with w>>wci, excited by multi-MeV runaway electrons in a low-density (ne~1019 m-3) plasma,...
Dr
Nicholas Eidietis
(General Atomics)
25/10/2018, 14:00
Poster
A finite-state off-normal and fault response (ONFR) system is presented that provides the required supervisory logic for robust disruption avoidance and machine protection in tokamaks. Robust event handling is critical for ITER and future large tokamaks, where plasma parameters will necessarily approach stability limits and many systems will operate near their engineering limits. The ONFR...
Dr
Jeffrey Herfindal
(Oak Ridge National Laboratory)
25/10/2018, 14:00
Poster
Experiments on DIII-D have injected multiple shattered pellets at different toroidal locations for the first time, as is planned for the ITER disruption mitigation system. Systematically varying the relative timing of the two pellets suggests that simultaneously injected pellets may impact the assimilation of each other, altering the resulting disruption characteristics compared to that due to...
Dr
Tyler Abrams
(General Atomics)
25/10/2018, 14:00
Poster
Measured intra-ELM (during ELMs) tungsten erosion profiles in the DIII-D divertor, acquired via W-I spectroscopy with high temporal and spatial resolution, are consistent with OEDGE+SDTrim.SP modeling including measured ion saturation currents and ion impact energies. If pedestal temperature rather than divertor conditions are used as input, quantitative agreement is observed, for the first...
Dr
Doohyun Kim
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
The effects of sawtooth on fast ion transport have been studied in reproducible, 2 seconds long sawtoothing L-mode discharges during the 2016 experimental campaign on National Spherical Torus Experiment Upgrade (NSTX-U). Experimental observations through Solid State Neutral Particle Analyzer (SSNPA) and Fast-Ion D-alpha (FIDA) diagnostics show that passing particles within the measured energy...
Dr
Boonyarit Chatthong
(Department of Physics, Faculty of Science, Prince of Songkla University)
25/10/2018, 14:00
Poster
This work uses CRONOS integrated predictive modelling code to simulate ion and electron temperatures of plasma scenarios based on a future Thailand tokamak. This small tokamak is planned to be installed at Thailand Institute of Nuclear Technology (TINT), under the collaboration of the Center for Plasma and Nuclear Fusion Technology (CPaF). The plasma transport includes both neoclassical, via...
Dr
Masanori Nunami
(National Institute for Fusion Science)
25/10/2018, 14:00
Poster
The first comprehensive analyses of kinetic simulations for anomalous and neoclassical transport of steady state multi-ion-species plasmas including impurity ions in helical systems are performed by gyrokinetic and drift-kinetic approaches.
To design the fusion reactors, the transport phenomena of plasma particles and heat need to be quantitatively predicted, and numerical simulation...
Dr
Robert Granetz
(MIT)
25/10/2018, 14:00
Poster
We find that disruption prediction using machine learning (ML), trained on
large databases containing only plasma parameters that are available in
real time on C-Mod, DIII-D, and EAST, differ substantially in performance
among the three machines, implying that a universal real time disruption
warning algorithm may be problematic. This could have important
implications for disruption...
Dr
Ezekial Unterberg
(Oak Ridge National Laboratory)
25/10/2018, 14:00
Poster
DIII-D carried out experiments using novel, isotopic tungsten (W) tracer sources in the outer divertor and has characterized how the W leakage from this region depends on botz the exact source location and ELM behavior. The W sources are toroidally-symmetric and poloidally-localized to two regions: (1) the outer strike point (OSP), a natural-W source; and (2) the far-target, i.e., 3-5 heat...
Dr
Orso Meneghini
(General Atomics)
25/10/2018, 14:00
Poster
An integrated modeling workflow capable of finding the steady-state solution with self-consistent core transport, pedestal structure, current profile, and plasma equilibrium physics has been developed, validated against several DIII-D discharges, and used to perform predictions for a 15 MA D-T ITER baseline scenario. Key features of the proposed core-pedestal coupled workflow are its ability...
Dr
Lei Qi
(National Fusion Research Institute of South Korea)
25/10/2018, 14:00
Poster
One of the long lived conundrums in ohmically heated plasmas is that the energy confinement time τ_E shows a transition from a linear regime proportional to the density (LOC) to a saturation regime (SOC) weakly dependent on the density. In the viewpoint of the first principle nonlinear global gyrokinetic simulations, we here present an investigation of LOC to SOC transition for the first time....
Mr
Giuseppe Telesca
(IPPILM Poland)
25/10/2018, 14:00
Poster
This paper is focused on the simulation of JET ELMy H-mode pulses pertaining to the baseline scenario with medium-high electron density, n_e, and auxiliary power, P_aux, in excess of 30 MW. The auxiliary heating is provided mostly by NBI, while ICRF heating does not exceed 5 MW. We have considered two pulses (Ip=3 MA, Bt= 2.8 T) at n_e = 6.5-7x10^19 m^-3 which show very high neutron rates and...
Seung Gyou Baek
(MIT PSFC)
25/10/2018, 14:00
Poster
Efficient lower hybrid current drive (LHCD) at high plasma density has been demonstrated on Alcator C-Mod for the first time with the reduction in the Greenwald fraction by raising the plasma current.
In order to attain, steady-state advanced tokamak operation, efficient off-axis current drive is required. LHCD is highly desirable because it has the highest efficiency of all technologies...
Morgan Shafer
(Oak Ridge National Laboratory)
25/10/2018, 14:00
Poster
Experimental evidence of the formation of multiple helicity island chains during the mode locking phase preceding plasma disruption is providing a clear picture for the understanding of locked-mode triggered disruptions. This emerging picture uses measurements from a new dual soft x-ray (SXR) tangential imaging system that measures localized internal perturbations in combination with local...
Mr
Anthony Leonard
(General Atomics)
25/10/2018, 14:00
Poster
A comparison of experiment and modeling of detached divertor plasmas in DIII-D is examined in the context of parallel energy transport due to electron conduction and plasma convection in order to validate and improve models used for divertor design. Power balance analysis is carried out to determine parallel heat flux and energy dissipation as a function of distance from the divertor target....
Dr
Siriyaporn Sangaroon
(Mahasarakham University)
25/10/2018, 14:00
Poster
A small tokamak is planned to be installed in Thailand at Thailand Institute of Nuclear Technology (TINT), Ongkarak campus in Nakorn Nayok, under the collaboration of the Center for Plasma and Nuclear Fusion Technology (CPaF). One of the great challenges subject in operating this tokamak is to gain better understanding of the impurities behavior because the impurities are responsible for the...
Prof.
Saskia Mordijck
(The College of William and Mary)
25/10/2018, 14:00
Poster
Exploration of particle transport behavior in multiple devices shows the importance of turbulence in determining particle confinement and the density profile. Behavior on CMOD indicates that as plasma parameters approach ITER, the pedestal and SOL become increasingly opaque. H-mode experiments with density pedestals approaching $4 \times 10^{20}$ $m^{-3}$, heated with the maximum auxiliary...
Dr
Zhanhui Wang
(Southwestern Institute of Physics)
25/10/2018, 14:00
Poster
Plasma fueling with higher efficiency and deeper injection is crucial to enable fusion power performance requirements at high density for next generation devices such as ITER. Compared to pellet injection fueling method, it penetrates shallower for the fueling methods of supersonic molecular beam injection (SMBI) and gas puffing (GP). SMBI is one method of deuterium gas jet injection. Fast...
Prof.
Eugenio Schuster
(Lehigh University)
25/10/2018, 14:00
Poster
Recent and ongoing experiments on DIII-D demonstrate the potential of model-based real-time optimization for the realization of advanced steady-state scenarios by tightly regulating the $q$ profile and $\beta_N$ (or the plasma energy $W$) simultaneously. A primary goal for the DIII-D research program over the next five years is to develop the physics basis for a high $q$ ($q_{\text{min}}>2$),...
Dr
Leopoldo Carbajal
(Oak Ridge National Laboratory)
25/10/2018, 14:00
Dr
Colin Chrystal
(General Atomics)
25/10/2018, 14:00
Dr
Nobuhiko Hayashi
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 14:00
Dr
Francis Casson
(UKAEA)
25/10/2018, 14:00
Dr
Simon Pinches
(ITER Organization)
25/10/2018, 14:00
Poster
The ITER Integrated Modelling & Analysis Suite (IMAS) is the software infrastructure that is being developed using expertise from across the research facilities within the ITER Members to meet the needs of the ITER Integrated Modelling Programme. It builds around a standardised representation of data described by a Data Dictionary that is both machine independent and extensible. Machine...
Dr
Adam McLean
(Lawrence Livermore National Laboratory)
25/10/2018, 14:00
Poster
Experimental observations of extreme ultraviolet resonance emissions in the divertor of DIII-D are used to quantitatively account for radiated power from molecular, atomic and ionized plasma constituents through the transition to detachment. Deuterium emission is found to be the primary emitter near the target scrape-off layer regions while the main impurity in DIII-D, carbon, is found to...
Dr
B.A. Grierson
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
Recent experiments in the DIII-D tokamak obtained low torque MHD-free H-mode discharges approaching ITER baseline conditions revealing mid-radius rotation profile hollowing associated with turbulent transport. This indicates that hollowing of toroidal rotation profiles that occurs prior to onset of large-scale MHD observed in low torque ITER Baseline conditions is not due to pre-existing MHD...
Dr
Luis F. Delgado-Aparicio
(Princeton Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
The computation of rotation-induced electrostatic potentials is currently being used to study the associated two-dimensional distribution of impurity density asymmetries in NSTX and NSTX-U plasmas. The main effect of toroidal rotation on heavy impurities is their radial displacement to the outer plasma, which result in a non-uniform distribution around a magnetic flux-surface. Due to the...
Dr
Jose Ramon Martin-Solis
(Universidad Carlos III de Madrid)
25/10/2018, 14:00
Prof.
Paul Terry
(University of Wisconsin-Madison)
25/10/2018, 14:00
Poster
An analytic saturation theory for toroidal ion temperature gradient turbulence is derived
from a well-known fluid model, providing the saturated levels of the unstable fluctuation, a
nearly conjugate stable mode, and the zonal flow, along with their dependencies on the
model parameters. The theory utilizes the eigenmode decomposition of the dynamical
equations, applies statistical closure,...
Dr
Akinobu Matsuyama
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 14:00
Dr
Weixing Wang Wang
(Princeton University Plasma Physics Laboratory)
25/10/2018, 14:00
Poster
Plasma self-generated current (e.g., the bootstrap current) contributes to the generation of poloidal magnetic field for plasma confinement in tokamaks, and also strongly affects key MHD instabilities. It is found that plasma turbulence may strongly influence self-driven current generation. This could have a radical impact on various aspects of tokamak physics. Our simulation study employs a...
Prof.
Hiroyuki Yamaguchi
(National Institute for Fusion Science, National Institutes of Natural Science)
25/10/2018, 14:00
Poster
Electrostatic potential $\Phi_{\rm NBI}$ generated by the neutral-beam-injection (NBI) to the plasma, and its effect on the neoclassical transport of carbon impurity ions in the Large Helical Device (LHD) are investigated for the first time by means of the global drift-kinetic simulations. The ripple-trapped beam ions of the perpendicular NBI (40keV) have been found to generate $\Phi_{\rm...
Mr
Debraj Mandal
(Institute for Plasma Research)
25/10/2018, 14:00
Poster
The physics of particle and energy transport in collision-less plasmas presents substantial challenge because of largely linear threshold based plasma turbulence are replaced by their nonlinear counterparts capable of operating at smaller amplitudes. An outstanding property for collision-less plasmas is the essential nonlinear character of coherent structures supported by them at small...
387.
The Effect of RMP ELM Control for ITER on Pedestal Pressure Compared to EPED No-RMP Predictions
Dr
Max Fenstermacher
(Lawrence Livermore National Lab)
25/10/2018, 14:00
Poster
The ITER baseline and alternate scenarios use 3D Resonant Magnetic Perturbation (RMP) fields to control ELMs, and therefore ITER operating scenario (IOS) analysis needs to include the effect of the 3D fields on the pedestal pressure and overall device performance. In IOS analysis, the pedestal pressure, for a given pedestal density, will be predicted with the EPED code. Neural net...
Dr
Florian M. Laggner
(Princeton University)
25/10/2018, 14:00
Poster
For wide ranges of operational parameters and in machines with different wall materials, the inter-ELM pedestal profile evolution was robustly linked to characteristic fluctuations, indicating that universal instabilities dominate the pedestal structure and its dynamics in between edge localized modes (ELMs). The presented results substantially advance the comprehension of the underlying...
Prof.
Lu Wang
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics, State Key Laboratory of Advanced Electromagnetic Engineering and Technology, School of Electrical and Electronic Engineering, Huazhong University of Science and Technology)
25/10/2018, 14:00
Poster
We present new results in the theory of turbulence driven intrinsic rotation and current. Both the intrinsic rotation and the intrinsic current driven by micro-turbulence are important for ITER. The former is critical for ITER due to its important role in suppressing MHD instabilities, since neutral beam injection may not provide enough external rotation drive in ITER. The latter is important...
Dr
Choong-Seock Chang
(Princeton Plasma Physics Laboratory and KAIST)
25/10/2018, 14:00
Poster
First-principles-based multiscale neoclassical-and-turbulent understanding of the impurity transport and its effect on the main plasma confinement is one of the most important subjects in magnetic fusion research. Seeding of impurity particles was found to improve the plasma confinement in the so-called “RI-mode” of operation [Weynants et al., Nucl. Fusion 39 (1999)]. More recently tungsten...
Dr
Par Strand
(Space, Earth and Environment, Chalmers University of Technology, SE-41296, Göteborg. Sweden)
25/10/2018, 14:00
Poster
The European Transport Simulator (ETS) [1] has been developed under the EUROfusion Integrated Modelling (EU-IM) effort [2] to meet the requirements for scenario development of burning plasmas. The ETS focuses both on interpretive and predictive modelling and is now being deployed for broader exploitation, e.g. on the JET computing infrastructure for close integration and use in support of JET...
Prof.
Kenichi Nagaoka
(National Institute for Fusion Science)
25/10/2018, 14:00
Mr
Stefan Buller
(Chalmers University of Technology)
25/10/2018, 14:00
Poster
Highly charged impurities both dilute plasmas and lead to radiation losses, and thus cannot be allowed to accumulate in the core of a magnetic confinement fusion reactor. For stellarators, the outlook has been particularly pessimistic, as early theories predicted that impurities would unavoidably be transported inwards in the core.
However, recent theoretical work has shown that strong...
Dr
Guoqiang Li
(Institute of Plasma Physica, CAS)
25/10/2018, 14:00
Poster
In the past two years, two major scenarios were developed on the EAST tokamak, the long pulse steady state scenario and the high $\beta_N$ scenario. For the steady state scenario, 100 s long pulse discharge was achieved with only radio frequency heating and current drive (CD) and it has improved confinement with H98~1.1. For the high $\beta_N$ scenario, the $\beta_N$ ~2.0 was sustained for ~2...
Mr
Christian Grisolia
(CEA)
25/10/2018, 14:00
SEE - Safety, Environmental and Economic Aspects of Fusion
Oral
During the ITER operation, plasma interacts with the machine plasma facing components (PFCs) through various physical processes and gives birth to particles from nanometer to tens of micron sizes that are called dusts in the fusion community. Depending on the plasma wall interaction, different types of dust will be created from almost spherical particles induced by high heat flux interaction...
Dr
Julio Martinell
(Nuclear Sciences Institute, National Autonomous University of Mexico)
25/10/2018, 14:00
Poster
Electrostatic drift waves produce transport by the E X B motion of a particle guiding center (GC) which can be studied from a Hamiltonian description where the electrostatic potential plays the role of the Hamiltonian. Here, the fluctuating potential is considered to be an infinite spectrum of waves, characteristic of weak turbulence, in two-dimensions. This is studied using a map that...
Prof.
Jiming Chen
(Southwestern Institute of Physics)
25/10/2018, 14:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The ITER enhanced heat flux (EHF) FW panel utilizes a Be/CuCrZr/316L(N) joint structure with hypervapotron (HVT) cooling channel in the CuCrZr heat sink to withstand cyclic surface heat flux up to 4.7 MW/m2. For Chinese CFETR and DEMO, the heat load will be much lower and a simple W/RAFM steel joint with cooling channels in the steel will be used. For all of them, reliable material bonding...
Dr
Thomas R. Barrett
(UkCCFE)
25/10/2018, 14:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The plasma-facing wall of the main chamber in DEMO will be unlike any current tokamak. The blanket first wall (FW) is to be actively-cooled reduced-activation steel (Eurofer) under a thin plasma-facing tungsten armour. To help control cost, modest misalignment of this wall must be tolerable at least with respect to a relatively quiescent divertor plasma flat-top equilibrium. However, with...
Dr
Robert Lunsford
(Princeton Plasma Physics Laboratory)
25/10/2018, 15:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The injection of boron (B) and boron nitride (BN) powders into ASDEX-Upgrade (AUG) H-mode discharges have shown the ability to effectively control tungsten influx in low density/collisionality operational regimes, similar to conventional boronization methods. A newly designed impurity powder dropper was installed onto AUG with 5m diameter BN powder, and 50 m B powder (99%+ purity) loaded...
Dr
Daniel Iglesias
(UK Atomic Energy Authority)
25/10/2018, 15:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The JET targets are the in-vessel components which receive the largest sustained thermal load. Operating instructions limit the energy and maximum surface temperature allowed for each shot, while IR cameras are used for protection during each discharge.
Surface delamination and radial cracks have been observed in the outboard tungsten-coated CFC tiles, while bulk tungsten special lamellas...
Dr
Arkadi Kreter
(Forschungszentrum Juelich)
25/10/2018, 15:40
MPT - Materials Physics and Technology
Oral
The first wall in ITER will be subjected to mixed species fluxes containing hydrogenic isotopes, helium produced in D-T reactions and radiator gases such as argon, neon or nitrogen. It is necessary to test how plasma-facing materials perform with respect to hydrogen retention under the mixed species plasma conditions. In this study, the influence of helium, argon, neon and nitrogen as plasma...
Dr
Gianfranco Federici
(Eurofusion Consortium)
25/10/2018, 16:40
This paper describes the status of the DEMO design activities performed in Europe and discusses the impact of some of the key requirements (such as electrical output, tritium self-sufficiency), the main constraints (e.g., those deriving from the tokamak-side and the Balance-of-Plant (BoP) / Power Conversion System (PCS)) on the systems design solutions and on the overall plant architecture....
Dr
Yoshiteru Sakamoto
(National Institutes for Quantum and Radiological Science and Technology)
25/10/2018, 17:00
Recent design progress of Japan's DEMO is presented regarding the engineering and physics conceptual design of a steady-state DEMO with a major radius of 8 m class and fusion power of 1.5 GW level. The design concept of divertor is similar to that of ITER. By considering the neutron irradiation environment, a Cu-alloy cooling pipe is used only in the large heat flux region, while a RAFM steel...
Dr
Gregory Wallace
(MIT Plasma Science and Fusion Center)
25/10/2018, 17:20
The DIII-D National Fusion Facility is advancing the science and technology of steady-state fusion plasma sustainment through the implementation of two first-of-a-kind radio frequency current drive systems: the "helicon" or fast wave in the lower hybrid range of frequencies (LHRF), and high field side (HFS) launch of the lower hybrid slow wave.
Using existing DIII-D discharges, we have...
Dr
Rajesh Maingi
(Princeton Plasma Physics Laboratory)
25/10/2018, 18:00
A. Wall conditioning and ELM control has played a crucial role in enabling access to record long H-mode pulses in EAST. Here we present new results where 1) a 2nd generation (2G) flowing liquid lithium (Li) limiter was inserted into the EAST midplane and used to mitigate plasma-materials interactions (PMI); 2) Li powder was injected to eliminate ELMs in upper-single null (USN) configuration...
Dr
Rajesh Maingi
(Princeton Plasma Physics Laboratory)
25/10/2018, 18:10
In this paper we report experimental results obtained, for the first time in the world, in a tokamak with a liquid tin limiter (TLL). The FTU TLL was realized by using a molybdenum tube covered with Capillary Porous System (CPS) made by stripes of tungsten felt filled with tin. The TLL can be cooled by flowing air and atomized water inside a copper pipe inserted in the molybdenum tube. To test...
Robert Goldston
(Princeton Plasma Physics Laboratory)
25/10/2018, 18:20
A lithium vapor-box configuration [1] has been proposed to provide volumetric radiative dissipation in the divertor region of tokamak plasmas. While recent experiments have achieved continuous vapor shielding in close proximity to a lithium coated target in Magnum-PSI [2], this approach seeks to provide controlled detachment far from the divertor target, in a lithium vapor cloud maintained...
Mr
Thomas Brown
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
A toroidal confinement facility study and development of a characteristic experimental device was undertaken to investigate a range of liquid metal divertor and first-wall concepts build on past and expected results from liquid metal experiments: the Lithium Tokamak Experiment (LTX), the National Spherical Torus Experiment Upgrade (NSTX-U), and the Experimental Advanced Superconducting Tokamak...
Dr
Robert Lunsford
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Dr
Yusuke Shibama
(NATIONAL INSTITUTES FOR QUANTUM AND RADIOLOGICAL SCIENCE AND TECHNOLOGY)
26/10/2018, 08:30
The JT-60SA is a superconducting coil tokamak, which is the project combined with Japanese national project and Japan-EU Satellite Tokamak Programme. The coil system is composed of 18 Toroidal Field (TF) coils, 6 Equilibrium Field (EF) coils and Center Solenoid (CS). The size of the TF coil is 7.5 m high and 4.6 m width. EF coils structures have 12 m in the maximum diameter. Thesse large...
Dr
Alberto Loarte
(ITER Organization)
26/10/2018, 08:30
Poster
The achievement of ITER fusion performance is based upon plasma operational scenarios in which the plasma is in the high confinement regime (H-mode) during the burning phase. The fusion power production level is predicted to strongly depend on the values of the pedestal plasma temperature and density on the inner side of the edge transport barrier (ETB). Similarly, the steep edge density and...
Dr
Daniel Iglesias
(UK Atomic Energy Authority)
26/10/2018, 08:30
Dr
Rajesh Maingi
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Prof.
laura savoldi
(Dipartimento Energia Politecnico di Torino)
26/10/2018, 08:30
The large Ohmic load (~20 MW/m2) of the wall of the resonant cavity of high-power gyrotrons, designed for tokamaks and stellarators for EC resonance heating and current drive to deliver a microwave power of the order of MW per unit, constitutes one of the major technological limiting factors, despite the small extension of the surface on which it is deposited. Even before reaching the material...
Dr
Holger Reimerdes
(Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), Lausanne, Switzerland)
26/10/2018, 08:30
Poster
The European roadmap for fusion energy has identified plasma exhaust as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the baseline scenario with a single null divertor (SND) and a high radiation fraction adopted for ITER will not extrapolate to a DEMO reactor, the EUROfusion consortium is assessing potential benefits and engineering...
Dr
Jaehyun Lee
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
The bifurcation of perpendicular rotation ($v_{\perp}$) at the transition of ELM-crash suppression has been measured using electron cyclotron emission imaging (ECEI) system on KSTAR. The ECEI revealed that the ELM crashes are suppressed along with a rapid reduction of $v_{\perp}$, which synchronizes with the transition into and out of the ELM-crash suppression. The $v_{\perp}$ bifurcation is...
Mr
Jae-Sun Park
(Korea Advanced Institute of Science and Technology)
26/10/2018, 08:30
Poster
A divertor detachment experiment in low confinement mode and $B\times \nabla B$ into the divertor was performed in KSTAR to investigate various divertor operation regimes. The low field side (LFS) target parallel particle flux $\Gamma_{\parallel}$ started roll-over first ($n_{e} = 2.0-2.5 \times 10^{19} m^{-3}$), and then the high field side (HFS) target $\Gamma_{\parallel}$ began roll-over at...
Prof.
Tomohiko Asai
(Nihon University)
26/10/2018, 08:30
Poster
The collisional merging experiments of field-reversed configurations (FRCs) at super Alfvénic velocity have been successfully initiated in the FAT-CM device at Nihon University. Drastic increase of the excluded-flux leading to the improved confinement performance of FRC has been observed. This process has an important role to realize FRC based high-beta reactor core to capture high-energy beam...
Dr
Vincenzo PERICOLI RIDOLFINI
(PoIPP)
26/10/2018, 08:30
Poster
The mitigating properties of the divertor advanced magnetic configurations on the target heat load have been analysed with the 2D edge code TECXY for the European DEMO. Particular emphasis is put on the snowflake minus, for which several variants have been proposed just to study this particular effect, where the distance between the two X points, the primary and secondary ones, is varied. In...
Dr
Takuya Goto
(National Institute for Fusion Science)
26/10/2018, 08:30
Conceptual design of a compact LHD-type helical fusion reactor FFHR-c1 has been conducted. This design focuses on a year-long electric power generation with as small a reactor size as possible by adopting the operation with auxiliary heating and innovative ideas for the design of engineering system. This design ensures the path to helical commercial power plants through the examination of...
Mr
Ammar Hakim
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
We describe results obtained from Gkeyll, a full-F continuum
gyrokinetic code, designed to study turbulence in the edge region of
fusion devices. The edge region is computationally very challenging,
requiring robust algorithms that can handle large amplitude
fluctuations and stable interactions with sheath boundary
conditions. Results of turbulence in a scrape-off layer (SOL)...
Dr
Ivan Vargas-Blanco
(Instituto Tecnológico de Costa Rica)
26/10/2018, 08:30
Poster
The small modular SCR-1 Stellarator (R = 247.7 mm, R/a = 6.2, ιa = 0.264) has an ECRH system of 2.45 GHz (5 kW) with an average magnetic field of 41.99 mT [1]. Few studies on conversion of electrostatic Bernstein waves under these conditions have been performed in Stellarators [2,3]. This work presents the results of converting electrostatic Bernstein waves in the SCR-1 Stellarator using the...
Ms
Gayathri V.
(Institute for Plasma Reserch, India)
26/10/2018, 08:30
Efficient design of Tritium Extraction System (TES) for the fuel cycle of any fusion reactor is very important to maintain the tritium breeding ratio and hence sustain the fusion reaction. Hydrogen Isotopes Removal System (HIRS) for Indian Tritium Breeder Blanket removes Q2 (Q = H, D or T) and impurities using Cryogenic Molecular Sieve Bed (CMSB) adsorber at 77K. The CMSB is maintained at...
Mr
bharatkumar doshi
(Institute for plasma research)
26/10/2018, 08:30
Steady state super conducting Tokamak (SST-1) is an indigenously built working experimental Tokamak at Institute for Plasma Research (IPR). The primary magnetic configurations and plasma shaping magnetic requirements are provided by Superconducting Magnet Systems (SCMS) comprising of sixteen superconducting D-shaped Toroidal Field (TF) magnets and nine superconducting Poloidal Field (PF)...
Mr
Brijesh Kumar Yadav
(Institute for Plasma Research, Bhat, Gandjinagar, India)
26/10/2018, 08:30
India is developing the lead–lithium cooled ceramic breeder as the blanket concept to be tested in ITER. In the Indian Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM), PbLi eutectic alloy is used as multiplier, breeder, and coolant for the CB zones, and Li2TiO3 ceramic breeder (CB) is used as a tritium breeding material. The outer box structure is made of India specific Reduced...
Robert Goldston
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Dr
Mattia Siccinio
(EUROfusion Consortium)
26/10/2018, 08:30
In order for the first fusion reactor DEMO to accomplish its mission, it is necessary to identify a plasma scenario which is at the same time performing in terms of fusion power generation and sufficiently stable to ensure the integrity and availability of the machine components for a long time. In the present work, the activities undertaken for this purpose by EUROfusion PMU are...
Mr
Naveen Rastogi
(Institue for Plasma Research)
26/10/2018, 08:30
Remote handling (RH) systems are highly challenging for application in the maintenance of fusion devices. The challenges include accurate handling of very heavy payloads using long cantilevered robotic arms with a dexterous manipulator. For the flexibility to execute dynamic tasks safely, these manipulators are typically controlled using a ‘man in the loop’ architecture. Haptic systems with...
Prof.
Yuichi Takase
(University of Tokyo)
26/10/2018, 08:30
The capacitively-coupled combline (CCC) antenna has been developed for current drive by the lower hybrid wave (LHW) on the TST-2 spherical tokamak. In order to excite a highly directional wave required for efficient current drive, an antenna array consisting of many elements is necessary, but it is impractical to feed each of these elements independently in a device with limited accessibility....
Dr
Sergey Ananyev
(NRC "Kurchatov Institute")
26/10/2018, 08:30
In the NRC “Kurchatov Institute” fueling systems (FS) concept for the DEMO-FNS facility incorporating components maintaining plasma parameters, tritium processing and breeding, is being developed. The FS computer model provides calculation functions using the computer code «FC-FNS». It allows to calculate gas flows, tritium inventories and losses in FS for steady-state operation mode.
Within...
Dr
Yoshiteru Sakamoto
(National Institutes for Quantum and Radiological Science and Technology)
26/10/2018, 08:30
Mr
Oliver Crofts
(RACE UKAEA B1 Culham Science Centre, Abingdon, Oxon, UK)
26/10/2018, 08:30
The development of fusion as a viable power source is moving from the science driven design of experimental devices to the engineering design considerations required to develop a feasible power plant. An effective maintenance plan is essential because the time in maintenance is potentially very large.
To be effective a maintenance plan must be outlined early in the plant design because it has...
Prof.
Shutaro Takeda
(Kyoto University)
26/10/2018, 08:30
Prof.
Chijin Xiao
(University of Saskatchewan)
26/10/2018, 08:30
Poster
In a recent experimental campaign in the STOR-M tokamak (*R/a* = 0.46/0.12 cm, *Bt* =0.65 T, *Ip* =22 kA), approximately 100 mg of lithium per load has been evaporated from a heated lithium reservoir and coated on the stainless-steel inner wall to study its effects on the tokamak discharge. The evaporators were designed, developed and supplied by General Fusion Inc.. Although four evaporators...
Prof.
Michiaki Inomoto
(The University of Tokyo)
26/10/2018, 08:30
Poster
Axial merging method is one of the candidates to provide center-solenoid-free start-up of high beta spherical tokamak (ST) plasma, in which two initially formed STs merge through magnetic reconnection in the presence of the guide (toroidal) magnetic field, which is perpendicular to the reconnection (poloidal) magnetic field. Magnetic reconnection between two STs is capable of heating the...
Ms
Neelam Shukla
(IIT Roorkee)
26/10/2018, 08:30
Poster
Tungsten has been planned to be used in the diverter region of International Thermonuclear Experimental Reactor (ITER) as it has the highest heat load capacity, highest melting point and more other favourable physical properties among the metals. Distinct ionic states of tungsten are predicted to be present from divertor to core of the ITER device. Thus, to understand the radiation emissions...
Mr
Juhyeok Jang Jang
(Korea Advanced Institute of Science and Technology)
26/10/2018, 08:30
Poster
Impurity seeding with noble gases, such as krypton (Kr), is regarded as a promising way to mitigate divertor heat loads. In this study, ELMs were successfully suppressed by Kr injection in the KSTAR divertor region and the relation between ELM behaviour and Kr amount was studied in KSTAR plasmas with 0.5 MA plasma current and 2.5 T toroidal field. Figures 1(a)-(c) show the plasma parameters...
Mr
Someswar Dutta
(Institute For Plasma Research)
26/10/2018, 08:30
The SST-1 Tokamak has 16 numbers of toroidal field (TF) coils and 9 numbers of super conducting poloidal field (PF) coils. They have been assembled and the in-accuracy in positioning of these coils is measured. The deviations in coil positions will generate error field and this will degrade the plasma performance. The error field produced by the TF coil misalignment can impact the plasma...
Padivattathumana N Maya
(ITER-India)
26/10/2018, 08:30
Dr
Jayhyun Kim
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
Since 2013 KSTAR campaign, we have investigated the effect of non-axisymmetric (NA) fields on the evolution of magneto-hydrodynamic (MHD) instabilities by using the error field (EF) correction coils. Locking and EF penetration were induced by the torque imbalance between the intrinsic rotation and external magnetic braking. Further increase of the n=1 EF resulted in minor and major...
Prof.
João P. S. Bizarro
(Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, 1049-001 Lisboa, Portugal)
26/10/2018, 08:30
Poster
Exact solutions have been obtained for the conservative part of a standard two-fluid (density plus vorticity) model of the scrape-off layer (SOL) which are of the travelling-wave type and describe transport of large-, machine-scale structures across the plasma cross-section (radially and/or poloidally). These conservative solutions can be of various forms and shapes, either extended or...
Mr
Inwoo Song
(Korea Advanced Institute of Science and Technology (KAIST))
26/10/2018, 08:30
Poster
In fusion plasmas with electron temperature of several keV, most of the tungsten (W) particles are in W27+ to W45+ ionic states, which emit line radiations of a few nm wavelength in the EUV range. Thus, a compact (63x44x18 cm3) advanced EUV spectrometer system (CAES) was recently developed [2] to simultaneously measure spectrally-resolved tungsten emission and spatially-resolved W density...
Dr
YoungMu Jeon
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
Reliable and robust resonant magnetic perturbation (RMP) on the edge-localized-mode (ELM) crash control is crucial for the success of ITER and beyond. In recent KSTAR experiments, a critical dependence of RMP-ELM coupling on the plasma shape was found to be as important as much as $\mathrm{q_{95}}$. In application of the low-n RMP fields, small variations in the lower triangularity by...
Dr
Giuseppe Mazzitelli
(ENEA)
26/10/2018, 08:30
Dr
Geert Verdoolaege
(Ghent University)
26/10/2018, 08:30
Poster
We report on an ongoing task within the ITPA concerning a revision of the global H-mode energy confinement scaling in tokamaks, known as IPB98(y,2). The objectives of the task are to update the database with data closer to ITER baseline and hybrid conditions, to expand the parameter range and include new data from devices with reactor-relevant metallic walls, to explore predictor variables and...
Prof.
satoshi konishi
(kyoto university)
26/10/2018, 08:30
Mr
Takuya Nagasaka
(National Institute for Fusion Science)
26/10/2018, 08:30
Dr
Mitsuru Kikuchi
(QST)
26/10/2018, 08:30
Dr
Himank Anand
(ITER Organization)
26/10/2018, 08:30
Poster
A real-time (RT) first wall (FW) heat load control system will be required at a very early stage of ITER plasma operations. The long pulse nature of the device imposes active cooling of all plasma-facing components (PFCs) and thus strict control of surface power flux density at all times. Plasma current ramp-up in limiter configuration on the beryllium FW panels (FWP) is foreseen for all ITER...
Prof.
Jaime Mora-Meléndez
(Instituto Tecnológico de Costa Rica)
26/10/2018, 08:30
The low aspect ratio Spherical Tokamak (ST) MEDUSA (Madison Education Small Aspect Ratio Tokamak) is currently being re-commissioned at the Instituto Tecnológico de Costa Rica, after it was donated by the University of Wisconsin-Madison, USA. The main characteristics of this magnetic confinement device are described as follows: plasma major radius of Ro < 0.14 m, plasma minor radius a < 0.10...
Dr
Hanni Lux
(CCFE, UKAEA)
26/10/2018, 08:30
During the pre-conceptual design phase of fusion devices such as the European demonstration fusion power plant (DEMO), systems codes provide a fast evaluation of optimal design points and highlight high impact areas. However, determining or evaluating a design point at such an early stage comes with uncertainties in many of the design parameters. These uncertainties are both associated with...
Dr
Arkadi Kreter
(Forschungszentrum Juelich)
26/10/2018, 08:30
Dr
Richard J. Buttery
(General Atomics)
26/10/2018, 08:30
Poster
A new theory-based integrated modeling of Core, Edge Pedestal, and Scrape-Off-Layer (CESOL) has been developed, validated and used to project core to boundary solutions for an upgrade to DIII-D that will develop the plasma physics path to a steady state fusion reactor. It also represents a significant step towards a whole device modeling (WDM). The simulation reproduces DIII-D high N...
Mr
Jeong-hun Yang
(Seoul National University)
26/10/2018, 08:30
Poster
During the current rise phase of tokamak discharges, evolving current density profiles are associated with the MHD fluctuations that are often held responsible for the confinement degradation, or even disruption, early in the discharge. Moreover, VEST, (Versatile Experiment Spherical Torus) for the NBI heated advanced tokamak regime, adopts the fast current ramp up Ohmic discharge, where the...
Dr
Sang Gon Lee
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
The toroidal rotation from pure ohmic discharges without any external momentum sources is one of the most fundamental types of self-generated intrinsic rotation for magnetic fusion researches. There have been reported a wide range of magnitudes, directions and abrupt reversals for ohmic toroidal rotation studies, no clear physical mechanisms are concluded to explain these intrinsic ohmic...
Dr
Hiroki Hasegawa
(National Institute for Fusion Science)
26/10/2018, 08:30
Poster
The ion inertial effects on the sheath-limited filament dynamics have been investigated with the three-dimensional (3D) electrostatic Particle-in-Cell (PIC) simulations. We have shown that the radial propagation speed of a sheath-limited filament becomes slightly slower in deuterium-tritium (D-T) plasmas than in light hydrogen (H) plasmas because of the gyro motion effect. The filament (blob)...
Dr
Joao Figueiredo
(EuFusionUk and PtIPFN)
26/10/2018, 08:30
JET upcoming deuterium-tritium campaign, DTE2, is scheduled to take place before the end of 2020. From a point of view of diagnostics developments, for many years JET diagnostics have been upgraded in order to provide adequate support for the scientific exploitation of a D-T campaign, with particular attention to the experimental and operational conditions expected during deuterium-tritium...
Mr
Piyush Prajapati
(Institute for Plasma Research)
26/10/2018, 08:30
As the demand for energy grows, futuristic energy sources like the D-T thermonuclear fusion using the magnetic confinement scheme called tokamak are being researched upon. It is generally presumed that a fusion blanket surrounds the tokamak plasma which absorbs the fusion neutrons, using their energy to convert into heat energy and nuclear transmutation with lithium to re-generate the lost...
Mr
Dikens Christian
(Institute for Plasma Research)
26/10/2018, 08:30
1.3 kW helium refrigerator/liquefier (HRL) system is installed and in operational at Cryogenic division of IPR since 2003. Steady State Super-conducting Tokomak consists of superconducting magnets which are cooled by cryogenic HRL plant. Three numbers of 315 kW asynchronous induction motors are used to drive helium screw compressors of HRL plant, therefore it is very essential to maintain the...
Prof.
Hongli Chen
(University of Science and Technology of China)
26/10/2018, 08:30
As one of typical blanket concepts for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of helium cooled solid breeder (HCSB) blanket was designed by USTC. Considering that electromagnetic load is one of the main concerns for the blanket module, a FEM (finite element method) model of the HCSB was developed and the electromagnetic analysis of the blanket module was...
Dr
Rui Ding
(UsORAU)
26/10/2018, 08:30
John Canik
(Oak Ridge National Laboratory)
26/10/2018, 08:30
Poster
We report on a new simulation capability for predicting plasma-surface interactions, including the evolution of the plasma-facing component (PFC) surface layer that is continually modified by contact with the fusion plasma. This involves a wide range of physical phenomena: our current model includes components for a) the scrape-off layer plasma including fuel ions and extrinsic impurities...
Dr
Vanni Antoni
(Consorzio RFX)
26/10/2018, 08:30
A key component of ITER is the heating Neutral Beam Injector (NBI) system, expected to be the main source of the input power necessary to reach fusion conditions. The nominal parameters of the ITER NBI (40 A negative H-/D- ion beam accelerated to 1 MeV and then neutralized) are so challenging that they require extensive international research and development activities. Reliable operation of...
Ms
shikha Binwal
(Jamia Millia Islamia (A Central University))
26/10/2018, 08:30
Capacitive coupled plasmas (CCP) have unique applications in microelectronic industries, besides they are also important in plasma interaction with material surfaces, such as near field region of ICRF antenna infusion devices. Systematic studies of these plasmas are concurrently carried in laboratory plasma devices to develop models to explain the anomalous behavior of plasma sheath...
Dr
Gregory Wallace
(MIT Plasma Science and Fusion Center)
26/10/2018, 08:30
Dr
Suk-Ho Hong
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
KSTAR has been involved in studying leading edge heat loads since 2014 by using series of multi-purpose, brazed W blocks (W-Cu-CuCrZr). They are mounted and assembled into two adjacent, inertially cooled graphite tiles installed in the outer divertor target region of KSTAR, within the field of view of an infra-red (IR) thermography system installed in an upper lateral port and to which special...
Mr
Atul Garg
(Institute for Plasma Research)
26/10/2018, 08:30
Current Feeder System (CFS) plays vital role in Superconducting (SC) fusion device, SST-1 (Steady state superconducting Tokamak). As, long pulse operation of the Tokamak and fusion reactors require high magnetic field to confine and shape the plasma, which is fulfilled through the superconducting magnets operating at high current ratings. CFS serves as an interface between the power supply...
Dr
Florian Koechl
(UKAEA)
26/10/2018, 08:30
Poster
The ability to describe the essential physics and technology elements needed to robustly simulate the operation of ITER is critical to being able to model the plasma scenarios that will run in ITER.
The Integrated Modelling & Analysis Suite (IMAS) is used to simulate the 15 MA DT baseline scenario operation, including a description of the plasma evolution from its core up to the plasma facing...
Gerd Gantenbein
(Karlsruhe Institute of Technology)
26/10/2018, 08:30
Within the Work Package Heating and Current Drive (WPHCD), coordinated by the Power Plant Physics and Technology Department of EUROfusion, detailed studies are ongoing, which cover three different systems for plasma heating and current drive. These are, namely, systems using electron cyclotron waves, ion cyclotron waves, and neutral beam injection. The studies are in line with the European...
Dr
Gianfranco Federici
(EUROfusion Consortium)
26/10/2018, 08:30
Mr
Michael Wigram
(University of York)
26/10/2018, 08:30
Poster
A means to handle the extreme power exhaust from tokamak-based fusion power reactors
remains to be demonstrated. Advanced divertor configurations have been proposed as potential solutions, including double-nulls, long-legs and magnetic field flaring with secondary X-points. Modelling of tightly-baffled, long-leg divertor geometries in the divertor test tokamak concept ADX has shown the...
Mr
Bibhu Prasad Sahoo
(Institute for Plasma Research)
26/10/2018, 08:30
Poster
The coupled plasma-neutral transport characteristics in the Scrape-Off Layer (SOL) produced by toroidally discontinuous limiter are essentially 3-dimensional and show strong deviation from the usual uniform SOL approximations. In a recently performed second-phase of EMC3-EIRENE plasma transport simulations for the limiter generated SOL of both original Aditya and Aditya Upgrade configurations,...
Dr
Sun-Ho Kim
(Korea Atomic Energy Research Institute, Daejeon, Korea)
26/10/2018, 08:30
Poster
An efficient heating and current drive in the central or off-axis region of tokamak plasma should be developed for the steady state operation of a tokamak fusion reactor. A fast wave within lower hybrid resonance frequency range(LHFW) could be a scheme for the current drive in a high-density, high-temperature reactor grade plasmas.[1,2] A proof-of-principle experiment was planned for the LHFW...
Mr
Randy Churchill
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
Understanding the physics governing the scrape-off layer is necessary in order to reliably predict machine and operation critical quantities, such as the heat flux width at the divertor, plasma-wall interaction, material migration, effect of divertor condition on the pedestal profile, etc. Among the most basic quantities to predict is how the density and temperature in the SOL change from an...
Ms
Swati Roy
(Institute for Plasma Research, Gandhinagar)
26/10/2018, 08:30
Steady-State Superconducting Tokamak-1 (SST-1) has 16 Toroidal field (TF) and 9 superconducting poloidal field (PF) coils rated for 10 kA DC. TF coils are connected in series and operated in DC condition, whereas PF coils are operated independently in pulse mode. SST-1 current feeder system (CFS) houses 9 pairs of PF superconducting current leads and 1 pair of TF superconducting current leads....
Mr
Kaname Kizu
(National Institutes for Quantum and Radiological Science and Technology)
26/10/2018, 08:30
To realize JT-60SA of the largest superconducting tokamak device in the world, the current feeder and helium pipes have been designed so as to have the flexible structure with bend and to be supported with octagonal shape. The control system for feeding current and helium has been also developed to operate 18 Toroidal coils, 6 Equilibrium Coils and a Central solenoid. The engineering solutions...
Yuri Shpanskiy
(NRC "Kurchatov Institute")
26/10/2018, 08:30
Further development of a fusion-fission hybrid facility based on superconducting tokamak DEMO-FNS continues in Russia for integrated commissioning of steady-state and nuclear fusion technologies at the power level up to 40 MW fusion and 400 MW fission reactions. This facility is considered as the main source of technological and nuclear science information in National program for development...
Mr
Jiming Chen
(Southwestern Institute of Physics)
26/10/2018, 08:30
Mr
Gaurang Mahesuria
(Ipr)
26/10/2018, 08:30
The Steady state superconducting Tokamak (SST-1) is medium size tokamak, which requires liquid nitrogen (LN2) cooled 80 K bubble shields for reducing direct static heat load from room temperature to superconducting magnets system (SCMS). Dedicated liquid nitrogen booster system has been installed and commissioned to cater 0.7 MPa / 80 K single phase flow for uniform temperature distribution...
Dr
Michael Lehnen
(ITER Organization)
26/10/2018, 08:30
Poster
The disruption mitigation system (DMS) is a key plant system to ensure the reliable and successful operation of ITER from the first experimental campaign onwards. The DMS baseline concept and design is based on present knowledge on disruption mitigation, which, nevertheless, remains subject to significant gaps in understanding, especially as concerns runaway electron (RE) formation and...
Prof.
Eugenio Schuster
(Lehigh University)
26/10/2018, 08:30
Poster
Tight regulation of the burn condition in ITER has been proven possible even under time-dependent variations in the fuel concentration by the use of robustification techniques. One of the most fundamental control problems arising in ITER and future burning-plasma tokamaks is the regulation of the plasma temperature and density to produce a determined amount of fusion power while avoiding...
roberto zanino
(dipartimento energia, politecnico di torino)
26/10/2018, 08:30
Poster
The steady-state power exhaust problem in future fusion reactors (e.g, DEMO) is considered as a major challenge along the path towards fusion electricity. Dedicated work packages are being devoted to this problem within EUROfusion and a dedicated facility (the Italian Divertor Tokamak Test – IDTT) is being designed in Italy. Among the possible solutions for this problem, a liquid metal (LM)...
Dr
Igor Kupriyanov
(A.A. Bochvar High Technology Research Institute of Inorganic Materials (JSC "VNIINM"))
26/10/2018, 08:30
Poster
The first wall panels of the ITER main chamber will be completely armored with beryllium. The primary reasons for the selection of beryllium as an armor material for the ITER first wall are its low Z, high oxygen gettering characteristics and also high thermal conductivity. During plasma operation in the ITER, beryllium besides low cyclic heat loads (normal events) will be suffered by high...
110.
Simulation of cross-separatrix edge plasma transport with the continuum gyrokinetic code COGENT
Dr
Mikhail Dorf
(Lawrence Livermore National Laboratory)
26/10/2018, 08:30
Poster
Axisymmetric (4D) simulations using the finite-volume code COGENT are performed to explore the role of ion kinetic effects in tokamak edge plasmas. The simulation model solves the long wavelength limit of the full-F gyrokinetic equation for ion species coupled to the 2D quasi-neutrality equation for electrostatic potential variations, where a fluid model is used for an electron response. The...
Prof.
Minyou Ye
(School of Nuclear Science and Technology, University of Science and Technology of China)
26/10/2018, 08:30
Poster
It is crucial to exhaust the huge power come from core plasma in future fusion reactor. For a fusion reactor of 1-2 GW fusion power, considering the auxiliary heating power and core radiation, ~200 MW will enter into the scrape-off layer (SOL) and exhausted in the divertor. To find an effective way to exhaust the heat power for future fusion reactor, snowflake divertor (SFD) [D.D. Ryutov,...
Xueqiao Xu
(Lawrence Livermore National Laboratory)
26/10/2018, 08:30
Poster
The BOUT++ code has been used to simulate edge plasma electromagnetic (EM) turbulent transport and to study the role of EM turbulence in setting the scrape-off layer (SOL) widths. More than a dozen tokamak discharges from C-Mod, DIII-D, EAST, ITER, and CFETR have been simulated with encouraging success. The simulation results reproduce the measured pedestal turbulence characteristics and the...
54.
SOL/Divertor Plasma Simulation of Diverging Magnetic Field Configurations for Advanced Divertors
Dr
Satoshi Togo
(Plasma Research Center, JpUTsukuba)
26/10/2018, 08:30
Poster
Handling heat loads onto divertor plates is one of the crucial issues. Advanced divertors expand the flux tube of a divertor plasma and reduce the heat load onto the divertor plate. A Super-X divertor (SXD) sets the outer target plate at a further position in major radius than an ordinary divertor (OD) leading to a largely diverging magnetic field (DMF). In order to simulate supersonic plasma...
Mr
HyunYeong Lee
(Seoul National University)
26/10/2018, 08:30
Poster
Solenoid free start-up scenario is the way to utilize loop voltage from the evolution of equilibrium field using outer PF coils. Also, it can be expected to be as an attractive start-up scheme in the fusion machines with low aspect ratio since flux from external inductance change can be utilized. The solenoid free start-up experiments using outer PF coils have been conducted in various...
Dr
Vipulkumar Tanna
(Institute for Plasma Research)
26/10/2018, 08:30
The SST-1 Machine consists of sixteen TF and nine PF superconducting coils. The cryo stable operation of these coils demand the operation temperature of 4.5 K. This technical requirement is met by 1350 W at 4.5 K helium cryogenic system and is operational since 2003. The SST-1 cryogenics systems include, helium as well as nitrogen cryo systems along with its storage, distribution and recovery...
Dr
Young-Seok Park
(Columbia University)
26/10/2018, 08:30
Poster
H-mode plasma operation in KSTAR has surpassed the n = 1 ideal MHD no-wall beta limit computed to occur at beta_N = 2.5 with l_i = 0.7. High beta_N operation produced beta_N of 3.3 sustained for 3 s, limited by tearing instabilities rather than resistive wall modes (RWMs). High fidelity kinetic equilibrium reconstructions have been developed to include Thomson scattering and charge exchange...
Dr
Anders Henry Nielsen
(Technical University of Denmark (DTU), Lyngby, Denmark)
26/10/2018, 08:30
Poster
The Scrape off Layer (SOL) plasma and its coupling with the edge dictate the performance of a discharge to a high degree – especially as all plasma has to go through the SOL, which is the main exhaust channel for the hot plasma. The understanding of the SOL plasma is a key topic in contemporary fusion research.
This contribution provides an overview of the modelling efforts of the plasma...
Mr
Hoseok Nam
(Kyoto University)
26/10/2018, 08:30
Dr
Thomas Barrett
(Culham Centre for Fusion Energy (CCFE))
26/10/2018, 08:30
Prof.
Yongkyoon In
(Ulsan National Institute of Science and Technology (UNIST))
26/10/2018, 08:30
KSTAR has demonstrated a divertor heat flux broadening during edge-localized-mode (ELM)-crash-suppression using ITER-like 3-row resonant magnetic perturbation (RMP) configurations for the first time. Over the last couple of years, we have established a robust methodology to fully suppress ELM-crashes using low-n RMPs. To address the ITER relevant ELM control, a systematic exploration of...
Dr
Si-Woo Yoon
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
For the realization of the fusion reactor, solving issues for high beta steady-state operation is one of the essential research topics for the present superconducting tokamaks and as a candidate of steady-state scenarios, characteristics of, so called, ‘high beta-poloidal’ discharges[1] is analyzed in depth for the capability of fully non-inductive operation with high bootstrap current...
Dr
Angel Ibarra
(CIEMAT)
26/10/2018, 08:30
Dr
Vladimir Minaev
(Ioffe Institute)
26/10/2018, 08:30
Globus-M was a compact spherical tokamak with unique features such as plasma column tightly fitted into the vacuum vessel and high NB heating power density. The toroidal magnetic field in it was limited to 0.5 T. Globus-M2 is an upgraded version of Globus-M machine with substantial increase of engineering parameters (the toroidal magnetic field up to 1 T, the plasma current up to 0.5 MA). The...
Dr
Francesca Poli
(PPPL)
26/10/2018, 08:30
Poster
Following recent characterization of the plasma termination phase from a multi-machine database [1], the ITER termination phase is being analyzed, to define uncertainties due to physics assumptions and to deficiencies in the modeling. Considerable modelling and development has been done on ITER termination scenarios, focussing on specific aspects: magnetic control with transport assumptions...
Dr
Marco Wischmeier
(IPP Garching)
26/10/2018, 08:30
Poster
This contribution presents an overview how research in power and particle exhaust studies relevant to next step devices have advanced our quantitative understanding. For a future fusion reactor, such as the european DEMO, a dissipative power fraction, $f_{diss}$, of $90\%\;-\;97\%$ would simplify the engineering demands on plasma facing components, PFCs. A quantitative understanding of the...
Dr
Devendra Sharma
(Institute for Plasma Research, Bhat, Gandhinagar, India)
26/10/2018, 08:30
Poster
The computational modelling activity of plasma transport in the Scrape-off Layer (SOL) region of Indian tokamaks Aditya and SST-1 has explored a range of aspects of SOL plasma transport in both the devices. While 2-dimensional computations using SOLPS have predictively addressed aspects of the phase-I of divertor plasma operation of the tokamak SST-1, complete 3-dimensional EMC3-EIRENE...
Mr
Aroh Shrivastava
(Institute for Plasma Research)
26/10/2018, 08:30
Evaluation of thermal profile inside breeding blanket is an important aspect for fusion reactor. Due to thermal neutron flux during steady state operation of future fusion reactor, breeder materials in the blanket will be at elevated temperature up to 900°C. However, during ITER pulse operation with 1800 s pulse length, the maximum estimated temperature is ~650°C. India specific Reduced...
Mr
Upendra Prasad
(Institute for Plasma Research)
26/10/2018, 08:30
Steady-state Superconducting Tokamak (SST-1) magnet system consists of NbTi/Cu based CICC (Cable-In-Conduit Conductor) wound Toroidal (TF) and Poloidal (PF) coils. The TF coils are wound in double pancakes (DP), whereas the PF coils are in DP as well as layered winding scheme. These coils are cooled down up to 5 K using force flow circulation of helium. The void fraction of helium within the...
Mr
Arvind Tomar
(Institute for plasma research Bhat Gandhinagar India)
26/10/2018, 08:30
Steady-State Superconducting Tokamak-1 (SST-1) has Sixteen Toroidal field (TF) and nine superconducting poloidal field (PF) coils[1]. TF coils are connected in series, whereas, PF coils are to be operated individually in pulse mode. TF coils are operating up to 2.5 T in steady state condition but PF coils have hydraulic as well as heat load issues [2]. In order to operate TF coils and PF coils...
Mr
Jungmin Jo
(Department of Energy Systems Engineering, Seoul National University)
26/10/2018, 08:30
Poster
For the purpose of fusion triton confinement study on KSTAR, square shaped scintillating fiber detector has been installed and tested during the 2017 KSTAR campaign. It is composed of scintillating fiber bundles which are immersed in the lead matrix. Totally 1,056 scintillating fibers whose cross-sectional area is 1 mm^2 are immersed. The scintillation light is detected by Hamamatsu R878...
Mr
Ritesh SUGANDHI
(Institute for Plasma Research, Gandhiangar, India)
26/10/2018, 08:30
The Large Volume Plasma Device (LVPD) [1] is a cylindrical shaped, linear device (length=3m,
diameter=2 ) dedicated in carrying out pulsed plasma experiments (tpulse ̃9-50ms )relevant to fusion
and Magnetospheric plasma. In the recent past, investigations are switched from active wave plasma
investigations to understanding of plasma turbulence of whistler and Electron Temperature...
Mr
Christian Grisolia
(CEA)
26/10/2018, 08:30
Dr
Raju Khanal
(Tribhuvan University)
26/10/2018, 08:30
Poster
In all bounded plasmas, plasma sheath plays an important role in its stability as well as in determining the particle fluxes and energies reaching the wall. Velocity variation as well as modulation frequency of ions in a magnetized plasma sheath has been studied for different obliqueness as well as strength of the field. Due to sharp gradients of physical parameters in the sheath region fluid...
Dr
Mark Gilbert
(CCFE Fusion Association)
26/10/2018, 08:30
Dr
Choongseok Chang
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
A serious concern for ITER operation is the ability for the divertor to withstand the steady plasma exhaust heat that will be deposited on the divertor surface along a narrow toroidal strip. A simple, data-based regression from experimental measurements in present devices shows we would have λq≲1mm for ITER operation at Ip=15 MA. However, it is questionable if such a simple extrapolation is...
Dr
Youwen Sun
(Institute of Plasma Physics, Chinese Academy of Scienses)
26/10/2018, 08:50
Mixed toroidal harmonic Resonant Magnetic Perturbations (RMPs) have been used on both EAST and DIII-D to reduce the threshold for Edge Localized Modes (ELMs) suppression and to spread the divertor heat flux. Experiments using mixed toroidal harmonic RMPs have validated predictions that divertor heat and particle flux can be dynamically controlled while maintaining ELM suppression in DIII-D....
Dr
Wolfgang Suttrop
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 09:10
Full suppression of Edge Localised Modes (ELMs) by magnetic perturbations (MP) in high-confinement mode (H-mode) plasmas has been obtained in ASDEX Upgrade (AUG) in a shape-match experiment with DIII-D [Nazikian, IAEA FEC 2016]. In contrast to previous scenarios where ELMs were mitigated by MP, full ELM suppression in AUG requires stronger shaping. This finding has been attributed to larger...
Mr
Guoliang Xiao
(Southwestern Institute of Physics，China)
26/10/2018, 09:30
ELM control is a key issue in the magnetic fusion reactor. Experiments for controlling ELMs have been performed in the HL-2A tokamak with several tools, including lower hybrid current drive (LHCD), laser blow-off (LBO) seeded impurities (Al, Fe, W) and supersonic molecular beam injected (SMBI) impurities (Ar, Ne). A beneficial effect of the pedestal deposited impurity injected by LBO on ELM...
Dr
Debasis Chandra
(Institute For Plasma Research, INDIA)
26/10/2018, 09:50
We report on nonlinear simulation studies of the dynamical behavior of ELMs under the influence of repetitive injection of pellets using the nonlinear 2-fluid code CUTIE. ELMs are excited by introducing a particle source in the confinement region and a particle sink in the edge region. High density pellets are injected repeatedly near the edge with different duty cycles, where a duty cycle...
Mr
Takuya Nagasaka
(National Institute for Fusion Science)
26/10/2018, 10:45
MPT - Materials Physics and Technology
Oral
The National Institute for Fusion Science (NIFS) developed the NIFS-HEAT in collaboration with Japanese universities. Previous heats exhibited brittle fracture of weld joints and cracking during tubing fabrication at room temperature, due to ductility loss caused by interstitial impurities, such as C, N and O. The total of interstitial impurity level of NH2 is almost half that of the US heat....
Dr
Rui Ding
(Institute of Plasma Physics, Chinese Academy of Sciences)
26/10/2018, 11:05
MPT - Materials Physics and Technology
Oral
The 3D Monte Carlo code ERO taking into account a material mixing surface model has been used to simulate tungsten (W) erosion and migration on EAST with an upper full W divertor and DIII-D with toroidally continuous W rings embedded in the divertor target. Modeling shows that the transport of carbon (C) impurities not only dominates the W sputtering source but also determines the overall...
Dr
Padivattathumana N. Maya
(ITER-India, Institute for Plasma Research, Bhat, Gandhinagar)
26/10/2018, 11:25
MPT - Materials Physics and Technology
Oral
Tungsten has emerged as divertor-plasma-facing material in fusion reactors due to its excellent thermal and mechanical properties as well as low tritium affinity. It is therefore essential to understand the behavior of tungsten in reactor-like conditions from the point of view of radiation damage and fuel retention. There is already a world-wide effort in creating a database of radiation...
Dr
Angel Ibarra
(CIEMAT)
26/10/2018, 11:45
MPT - Materials Physics and Technology
Oral
The need of a neutron source for the qualification of materials to be used in future fusion power reactors have been recognized in the European (EU) fusion programme since many years. The construction and exploitation of this facility is presently considered to be in the critical path of DEMO. This issue prompted the EU to launch activities for the design and engineering of the IFMIF-DONES...
Dr
Mark Gilbert
(CCFE)
26/10/2018, 12:05
SEE - Safety, Environmental and Economic Aspects of Fusion
Oral
Waste-production predictions for the future demonstration fusion power plant (DEMO) are necessary to produce an accurate picture of the likely environmental and economic costs of radioactive waste disposal at end-of-life (EOL). Even during the conceptual stage of DEMO design it is important to perform waste assessment so as to avoid potential surprises caused by design flaws that could lead...
Dr
Marcin Jakubowski
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
26/10/2018, 14:00
Poster
Many present and future large magnetic fusion experiments need to consider the 3D topology of the heat and particle exhaust either due to application of external magnetic perturbations to mitigate type-I ELMs or because it is typically inherent to the magnetic configuration of the device (e.g. LHD or W7-X). In both cases, the scrape-off layer forms heterogeneous 3D structures of field lines...
Dr
Vladimir Vershkov
(ITF NCR "Kurchatov Institute")
26/10/2018, 14:00
Mr
Riccardo Ragona
(Laboratory for Plasma Physics, LPP-ERM/KMS)
26/10/2018, 14:00
Travelling Wave Array (TWA) antennas distributed all along the periphery of the tokamak are presently considered as Ion Cyclotron Resonance Frequencies (ICRF) heating solution for the DEMO reactor. Compared to the conventional ICRF antenna systems currently in use or designed for future machines like ITER, the TWA consists of antenna sections integrated in the breeding blanket all around the...
Mr
ZUBIN SHAIKH
(DEPARTMENT OF PHYSICS, SAURAHTRA UNIVERSITY, RAJKOT, INDIA)
26/10/2018, 14:00
The confinement by multi-cusp magnetic field configuration is being revisited in prospect of developing a Negative Ion Beam source for heating the plasma in fusion devices. For this, an experimental device namely the Multi-cusp Plasma Device (MPD), has been constructed to study the physics of plasma confinement in a multi-cusp configuration. In this experiment alkali ions of low ionization...
Mr
Alexey Altukhov
(Ioffe Institute)
26/10/2018, 14:00
Dr
Roberto Cavazzana
(Consorzio RFX)
26/10/2018, 14:00
Poster
The RFX toroidal device (R – major radius=2.0 m, a - plasma minor radius=0.457 m, b - shell minor radius=0.535 m; in operation 1992-1999) was designed to be operated in Reversed Field Pinch (RFP) configuration with a plasma current up to 2 MA. RFX-mod (R=2.0 m, a=0.459 m, b=0.512 m; in operation 2004-2015) was then equipped with 192 independently driven full coverage saddle coils to achieve...
Prof.
Bernhard Unterberg
(Forschungszentrum Jülich)
26/10/2018, 14:00
Poster
Tungsten is envisaged as plasma-facing material in fusion reactors because of its small tritium retention and low erosion rate as well as its high melting point and high thermal conductivity. However, its intrinsic and operation-induced brittleness and the unacceptably high oxidation rate at high temperatures pose challenges for manufacturing, component lifetime and safety. The development of...
Mr
amitkumar patel
(institute for plasma research)
26/10/2018, 14:00
The positive or negative ion sources which form the primary component of neutral beam injection (NBI) in controlled nuclear fusion using magnetic confinement have to meet simultaneously several demanding requirement like to produce high current, high energy and low-emmitance stable H- ion sources and to confine them etc [1]. It is very well known that multi cusp magnetic fields can confine...
Dr
Carsten Killer
(Max-Planck-Institute for Plasma Physics, Greifswald, Germany)
26/10/2018, 14:00
Poster
Wendelstein 7-X (W7-X) recently concluded its first operation phase (OP1.2a) featuring an island divertor. In this concept, the heat and particle exhaust to the divertors is governed by intrinsic three-dimensional magnetic islands at the plasma edge. In order to establish high performance plasmas with safe divertor operation, a comprehensive understanding of the island divertor physics is...
Mr
Baurzhan Chektybayev
(Institute of Atomic Energy of National Nuclear Center of Republic Kazakhstan)
26/10/2018, 14:00
In the paper is described concept of non-contact temperature measuring technique of metallic surface is currently being developed for KTM tokamak. Suggested technique is based on using thermographic camera and infrared carbon dioxide laser (CO2) with 10.6 micrometer wavelength. The pulsed IR laser radiation is used to observe changes in the emissivity of the body. This information will give...
Mr
Jaewook Kim
(KAIST)
26/10/2018, 14:00
Poster
We perform a correlation analysis to explore how the magnetic Kubo number evolves during and after an abrupt edge pedestal collapse generating stochastic magnetic fields in the simulation. During abrupt edge pedestal collapse caused by type-I ELM (Edge Localized Mode), the stochastic magnetic field is thought to be a possible way to induce significant cross-field diffusion. We analyze the...
Dr
Florian Effenberg
(Department of Engineering Physics, University of Wisconsin - Madison)
26/10/2018, 14:00
Mr
Kartik Mohan
(ITER-India,IPR)
26/10/2018, 14:00
ITER require 20 MW of RF power to a large variety of plasmas in the Ion Cyclotron frequency range for heating and driving plasma current. Eight RF sources of 2.5MW RF power level each collectively will accomplish the above requirement. Each RF source consists of Solid State Power Amplifier (SSPA), driver, and end-stage, above which driver and end-stage amplifier are a tube (Tetrode/Diacrode)...
Dr
Jitendra Kumar
(Institute for Plasma Research)
26/10/2018, 14:00
SYstem for Microwave PLasma Experiments (SYMPLE) is an experimental system set up at the Institute for Plasma Research (IPR), Gandhinagar, India, to investigate the physics of linear and nonlinear interaction of high-power microwave (HPM) with plasma. BWO based HPM source, proposed to be used for these studies, generates pulsed (~50 ns) microwave power of ~500MW at 3GHz frequency in TM01...
Mr
TARUN KUMAR SHARMA
(ITER-India, Institute for Plasma Research)
26/10/2018, 14:00
The ITER Cryostat, the largest stainless steel vacuum pressure chamber ever built which provides the vacuum confinement to components operating in ITER ranging from 4.5 k to 80 k. Cryostat Design Model was qualified[1] by ITER. As a Safety Important Class system, Design qualification at every change in its development and installation phases is mandatory. The Cryostat system is currently at...
Mr
Rajiv Sharma
(Institute for Plasma Research (An Autonomous Institute under Department of Atomic Energy,Govt. of India))
26/10/2018, 14:00
Electrical insulation breaks are very critical component of large-scale fusion devices employing superconducting magnets. The electrical insulation breaks developed for the requirement of up gradation of hydraulics for the superconducting polodial field coils (SC) of SST-1 fusion machine. The electrical insulation breaks have been installed in the hydraulic, validated and sustained the...
Mr
MANOJKUMAR PATEL
(PATEL)
26/10/2018, 14:00
ITER-India is developing Ion Cyclotron Heating & Current Drive (ICH&CD) RF source in the frequency of 35 to 65 MHz. Three cascaded amplifiers along with low power RF section, AC/DC power supplies and controls will be used for getting MW level RF power from one source. In the present configuration, two tube based tuned amplifiers, i.e. driver (150 kW) and final (1.7 MW) stage amplifiers are...
Dr
BANDYOPADHYAY MAINAK
(ITER-INDIA, INSTITUTE FOR PLASMA RESEARCH)
26/10/2018, 14:00
The characteristics of a negative hydrogen ion (H-) source and its neutralization mainly determine the performance of a negative ion based neutral beam injector (NNBI) performance. Ion source possesses many technological challenges in terms of production of uniform, extracted and accelerated negative ion beam current and also its transport to the tokamak plasma or the beam dump without...
Mr
AKHIL JHA
(ITER-INDIA, INSTITUTE FOR PLASMA RESEARCH)
26/10/2018, 14:00
ITER-India is responsible for delivery of 8+1(prototype) RF sources to ITER project. Each RF source will provide 2.5MW of RF power at VSWR 2:1 in the frequency range of 35 to 65MHz. Eight such RF sources will generate total 20MW of RF power. Two RF chains containing three high power amplifiers (HPA1, HPA2 and HPA3) need to be combined to build an RF source. HPA2 and HPP3 are RF tube based...
Dr
Youwen Sun
(Institute of Plasma Physics, Chinese Academy of Scienses)
26/10/2018, 14:00
Dr
Minjun J. Choi
(National Fusion Research Institute)
26/10/2018, 14:00
Dr
Ahmet Y. Aydemir
(National Fusion Research Institute, Daejeon, Korea)
26/10/2018, 14:00
Poster
In the simplest, magnetohydrodynamic (MHD) description of the plasma equilibrium, rapid transport along the field lines leads to a state where the plasma density and temperature are constant on flux surfaces, exhibiting symmetry in both the poloidal and toroidal directions.
This idealization, however, breaks down at the plasma edge where both the magnetic topology and various perpendicular...
Mr
Guoliang Xiao
(Southwestern Institute of Physics，China)
26/10/2018, 14:00
Dr
Eleonora Viezzer
(University of Seville)
26/10/2018, 14:00
Poster
Heat and momentum transport play a key role in achieving high confinement in fusion plasmas. Recent advances in the diagnostic capabilities at AUG now allow us to measure the edge profiles on a sub-ms to ms time-scale and with a spatial resolution of less than 5 mm, making it ideal to study the profile recovery after an ELM crash. Here, we present the dynamic behaviour of the energy and...
Dr
Athina Kappatou
(Max-Planck-Institut für Plasmaphysik, Garching, Germany)
26/10/2018, 14:00
Poster
The presence of fusion-produced helium is fundamentally connected to the performance of a fusion reactor. Not only will He ash dilute the fusion fuel if not removed promptly, but the presence of He in a D plasma is reported to negatively affect the plasma confinement [1]. Furthermore, He plasmas are a choice for the ITER non-nuclear phase, but the energy confinement in such plasmas is...
Chang Liu
(Princeton Plasma Physics Laboratory)
26/10/2018, 14:00
Poster
The effects of kinetic instabilities on the dynamics of runaway electrons in momentum space is investigated using a newly-developed simulation model, and the anomalous dissipation and the fast pitch angle scattering of runaway electrons in low energy are explained. The interaction of runaway electron avalanche and the kinetic instabilities are studied self-consistently using quasilinear model....
Dr
Sebastijan Brezinsek
(Forschungszentrum Jülich)
26/10/2018, 14:00
Mrs
Manika Sharma
(Institute for Plasma Research)
26/10/2018, 14:00
The evolution of data acquisition system (DAS) for steady-state operation of Tokamak has been technology driven. Steady-state Tokamak demands a data acquisition system which is capable enough to acquire data losslessly from diagnostics. The needs of loss less continuous acquisition have a significant effect on data storage and takes up a greater portion of any data acquisition Systems. With...
Dr
Wolfgang Suttrop
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Dr
Gregory Wallace
26/10/2018, 14:00
Mr
Pablo Rodriguez Fernandez
(UsPSFC)
26/10/2018, 14:00
Dr
Timothy C. Luce
(General Atomics)
26/10/2018, 14:00
Prof.
Thomas Sunn Pedersen
(Max Planck Institute for Plasma Physics)
26/10/2018, 14:00
Mr
Michael Houry
(CEA)
26/10/2018, 14:00
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Dr
Annika Ekedahl
26/10/2018, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Dr
Lionello Marrelli
(Consorzio RFX)
26/10/2018, 14:00
Poster
In this contribution the main achievements of the RFX-mod Reversed Field Pinch (RFP) are summarized as the basis for a substantial upgrade of the device. The RFX-mod active MHD control system successfully controlled MHD instabilities such as Resistive Wall Modes and mitigated localized Plasma Wall Interaction by avoiding Tearing Modes wall-locking. This allowed producing the highest RFP plasma...
Inessa Bolshakova
(Lviv Polytechnic National University)
26/10/2018, 14:00
Dr
Jugal Chowdhury
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543-451, USA)
26/10/2018, 14:00
Poster
The X-point height relative to the divertor plates may cause difference in the neutral particle penetration into pedestal and have impact on the pedestal physics in H-mode. In the present work, we utilize the total-f global gyrokinetic neoclassical code XGCa to study the X-point height effect on the ExB flow profile in a JET-like H-mode pedestal in a realistic JET-like divertor geometry and...
Dr
Jae-Min Kwon
(National Fusion Research Institute)
26/10/2018, 14:00
Dr
Francois Ryter
(Max-Planck-Institut fuer Plasmaphysik)
26/10/2018, 14:00
Poster
Turbulence-driven ion heat transport in tokamak H-modes is driven by
the ion temperature gradient (ITG) instability,
while electron heat transport is driven by the ITG, trapped electron
mode (TEM) and/or electron temperature gradient (ETG) instabilities.
These three instabilities appear above their respective threshold in
normalized temperature gradient
(R/LT) and drive transport.
We...
Mr
Sergey Bozhenkov
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
26/10/2018, 14:00
Poster
In this contribution we present details of recent W7-X pellet injection experiments and discuss properties of the achieved plasmas. Hydrogen pellet injections allowed to raise the electron density above $1.2 \cdot 10^{20}$ m$^{−3}$ and to establish: (i) operation above the cut-off for the X2 polarization of the 140 GHz electron cyclotron resonance heating (ECRH); (ii) stable divertor heat flux...
Mr
Raymond O'Neill
(General Atomics)
26/10/2018, 14:00
R.C. O’Neill1, M. Brookman1, J.S. deGrassie1, B. Fishler1, M. LeSher1, C. Moeller1, C. Murphy1, A. Nagy2, M. Smiley1, J. F. Tooker1, H. Torreblanca1
1General Atomics, PO Box 85608, San Diego, California 92186-5608, USA
2 Princeton Plasma Physics Laboratory, Princeton NJ 08543, USA
Corresponding author: oneill@fusion.gat.com
A new current drive system is being designed and...
Dr
Klaus Hallatschek
(Max-Planck-Institute for Plasma Physics)
26/10/2018, 14:00
Poster
Gyrokinetic and non-local fluid codes have complementary limitations in the tokamak
edge. To arrive at a common basis, the gyrokinetic code CGYRO and the non-local
two-fluid code NLET have both been applied to identical parameters sets ranging from
resistive ballooning turbulence - approaching the collisional fluid limit - relevant
to the edge of a tokamak, up to high-gradient kinetic ITG...
331.
Impact of an edge resonant transport layer on fast-ion confinement in the ASDEX Upgrade tokamak
Mr
Joaquin Galdon-Quiroga
(University of Seville)
26/10/2018, 14:00
Poster
An edge resonant transport layer has been found to explain many aspects of fast ion confinement under symmetry breaking 3D edge perturbations, such as edge localized modes (ELMs) and externally applied magnetic perturbations (MPs).
Experimental measurements in the ASDEX Upgrade (AUG) tokamak show that fast ion losses in the presence of symmetry breaking 3D fields strongly depend on the...
Dr
Mike Dunne
(IPP-Garching)
26/10/2018, 14:00
Poster
Pedestal data from ASDEX Upgrade (AUG) and Alcator C-Mod are presented. Scans of impurity content have been performed in both machines, reaching states where the outer divertor is partially or fully detached. The impact of impurity seeding on pedestal structure is compared. In the analysed scenarios, nitrogen seeding increases the achievable pedestal top pressure in AUG, while excessive...
Dr
Matthias Willensdorfer
(IPP Garching)
26/10/2018, 14:00
Poster
One method to mitigate or even suppress the repetitive impulsive energy loss due to edge localised modes (ELMs) is the application of externally applied non-axisymmetric magnetic perturbation (MP)-fields.
In high confinement mode (H-mode) plasma, these externally applied MP-fields excite marginally stable ideal kink modes at the edge, which amplify the MPs. These kink modes cause a...
Mr
Chandra Kishor Gupta
(Institute For Plasma Research)
26/10/2018, 14:00
This paper conceptualizes shunt active power filter (SAPF) using synchronous-reference- frame (SRF) theory to mitigate the harmonics present in the power system. The shunt active power filter injects a suitable compensating current at a point called point of common coupling (PCC) so that the harmonics present in the line are cancelled out and sinusoidal nature of current waveforms is restored....
Mr
Rakeshkumar Patel
(Institue for Plasma Research)
26/10/2018, 14:00
The static heat loads on the 80 K thermal shields of SST-1 will be removed using single phase liquid nitrogen cooling at 0.7 MPa. The single phase liquid nitrogen is obtained using 80 K liquid nitrogen booster system. Booster system is in form of three storey building as pump cryostat at bottom, sub-cooler vessel cryostat at middle and pressurized vessel cryostat at upper. Boosting system...
Diego del-Castillo-Negrete
(Fusion Energy Division. Oak Ridge National Laboratory)
26/10/2018, 14:00
Poster
The dynamics of runaway electrons (RE) is a complex process and, although significant progress has been made in the understanding of individual isolated pieces of the puzzle, a predictive capability calls for an Integrated Simulation (IS) effort. In this presentation we report on recent progress on this problem. The goal is to use the BMC method [1] to couple a kinetic description of the RE...
Dr
Donald Spong
(Oak Ridge National Laboratory)
26/10/2018, 14:00
Poster
Runaway electrons are of significant interest in tokamaks due to their potential for damage to plasma facing components. Runaways are of particular concern following disruptions when the plasma undergoes a thermal quench and a subsequent current quench; these lead to large loop voltages that can rapidly create runaways. Due to the risks of performing intense runaway experiments, the generation...
Dr
Novimir Pablant
26/10/2018, 14:00
Prof.
Jean-Marie Noterdaeme
(Max Planck Institute for Plasma Physics)
26/10/2018, 14:00
Poster
Significant progress in applying ICRF power to ASDEX Upgrade (AUG) has been achieved in the last years; this progress has been associated with a similar progress in our understanding and capability to model the relevant processes. The two main challenges of the ICRF system (power coupling and impurity production) have been tackled successfully.
First, the outer mid-plane gas injection...
Dr
Katsumi Ida
(National Institute for Fusion Science)
26/10/2018, 14:00
Dr
Carlos Silva
(IST/IPFN)
26/10/2018, 14:00
Poster
Information of the plasma density is essential for the study and operation of magnetically confined fusion devices. Microwave reflectometry appears as an attractive diagnostics due to its high temporal and spatial resolution and its application to profile as well as fluctuation measurements.
The microwave reflectometry systems developed by IST for ASDEX Upgrade consist of: (i) multi-band...
Dr
Eric Nardon
26/10/2018, 14:00
Mr
Hiteshkumar Kantilal Patel
(ITER India, Institute for Plasma Research)
26/10/2018, 14:00
High heat flux components form the primary interface of thermal management of injectors in the fusion devices. The requirement for such application varies from 1 to 10MW/m2. UHV compatibility is the inherent characteristics of such components also manufacturing processes involves the development of specific material, process qualification of special process like EB welding and component...
Dr
Jeremy Lore
(ORNL)
26/10/2018, 14:00
Poster
Experiments were performed in short pulse operation (OP1.2) on the Wendelstein 7-X (W7-X) stellarator using a set of five magnetic configurations that were designed to mimic the topology and resultant divertor fluxes of a high-power long-pulse scenario that is predicted to cause component overload. These experiments demonstrated the capability of edge transport simulations to accurately...
Mr
Jayant Patel
(Institute for Plasam Research, Bhat Indira Bridge, Gandhinagar, Gujarat, India)
26/10/2018, 14:00
Institute for Plasma Research has 1.3 kW helium refrigerator/liquefier (HRL) cryogenics system, which is in operational state since 2003. The cryogenic HRL plant used to cool down the magnets of Steady State Super-conducting Tokomak (SST-1). Three identical Mycom make helium screw compressors with Fimet make 315 kW Electrical Motor, Oil removal system operate to supply high-pressure helium...
Dr
Yves Peysson
(CEA)
26/10/2018, 14:00
Poster
The sudden termination of a plasma discharge known as a major disruption is a well-identified difficulty from the beginning of tokamak research, which remains still today particularly problematic for the design of a reliable fusion reactor. The key questions are principally related to the growth rate of relativistic electron population, closely linked to the level of the critical electrical...
Dr
Mireille SCHNEIDER
(ITER Organization)
26/10/2018, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Oral
The ITER low activation phase consists of H and He plasmas, split into Pre-Fusion Power Operation phases 1 and 2 (PFPO-1 and PFPO-2). The PFPO-1 phase will include 20 MW of Electron Cyclotron Resonance Heating (ECRH) and possibly 10 MW of Ion Cyclotron Radio Frequency Heating (ICRH), while the PFPO-2 phase will include the full Heating and Current Drive (H&CD) capabilities, i.e. 73 MW of H&CD...
Dr
Mireille SCHNEIDER
(ITER Organization)
26/10/2018, 14:00
Dr
Raghvendra Singh
(National Fusion Research Institute)
26/10/2018, 14:00
Poster
Raghvendra Singh1, Hogun Jhang1 and Maolin Mou2, 3
1National Fusion Research Institute, Daejeon 305-333, Republic of Korea
2College of physical Science and Technology, Sichuan University, 610065 Chengdu, China 3Key Laboratory of High Density Physics and Technology of Ministry of Education, Sichuan University, Chengdu, 610064, China
Email address: rsingh129@nfri.re.kr;...
Olivier Agullo
(Aix-Marseille Université)
26/10/2018, 14:00
Dr
Vinodh Kumar Bandaru
(Max-Planck-Institute for Plasma Physics, Garching)
26/10/2018, 14:00
Poster
Uncontrolled termination of post-disruption runaway electron (RE) current can cause deep localized melting of the first wall and this poses a serious challenge to the successful operation of fusion grade tokamaks, including ITER. Since the deconfinement of REs depends on the timescale of flux surface reformation and the plasma stability itself is affected by the runaway current, the...
Dr
Guanqi Dong
(SWIP)
26/10/2018, 14:00
Poster
Quiescent H-mode (QH-mode) was first discovered in DIII-D as an ELM-free H-mode regime, which is usually accompanied by the presence of edge harmonic oscillations (EHOs). EHOs are believed to provide necessary transport to eliminate ELMs by dynamics of the plasma itself. The saturated kink-peeling mode has been suggested as a possible candidate for EHO. In this work, we consider another...
Dr
Debasis Chandra
(Institute For Plasma Research, INDIA)
26/10/2018, 14:00
Dr
Nathaniel M. Ferraro
(UsPPPL)
26/10/2018, 14:00
Poster
Vertical displacement events (VDEs) where the plasma moves rapidly towards the wall can cause large electromagnetic forces on the vessel structures with possible damaging effects for large tokamaks. Non-axisymmetric modes developing during the VDE can lead to asymmetric, sometimes rotating forces on the vessel which can be even more severe. Large-scale 3D simulations play a crucial role on the...
Dr
Yang Li
(Department of Engineering Physics, Tsinghua University, Beijing 100084, China)
26/10/2018, 14:00
Poster
Meso-scale size structures including the blobs in the edge plasma can not only transport particle and heat out, but may also contribute to the plasma poloidal/toroidal rotation, namely, the momentum transport.[1] Turbulent parallel momentum stress can be divided into three components, which are diffusive, covective and residual parts. In the presented work, the triplet nonlinear term is...
Dr
Ulrich Fischer
(Karlsruhe Institute of Technology)
26/10/2018, 14:00
The European Roadmap to the realisation of fusion energy considers the stellarator concept as a possible long-term alternative to a tokamak fusion power plant (FPP). A corresponding R&D programme is conducted by the EUROfusion consortium to advance the stellarator concept with the scientific exploitation of the W7-X experiment. The aim is to optimise the stellarator performance, prove the...
Mr
Mahesh Ghate
(Institute For Plasma Research)
26/10/2018, 14:00
Fusion relevant high field superconducting magnets require large current carrying conductor of the order of tens of kilo-Amperes. High current carrying the cable in conduit conductor (CICC) are based on low-temperature NbTi and Nb3Sn superconductors. The manufacturing of superconducting cable is carried out by twisting required strands into the desired configuration by application of tensile...
Mr
JATINKUMAR PATEL
(INSTITUTE FOR PLASMA RESEARCH)
26/10/2018, 14:00
Electron Cyclotron Resonance Heating (ECRH) is one of the essential RF heating system used for pre-ionization and heating experiments in Aditya and SST1 tokamak. The 42 GHz gyrotron system capable of delivering 500kW RF power for 500ms has been installed for operation with Aditya and SST1 tokamak. Gyrotron operation requires a systematic and sequential controlled operation of different...
Ms
Harshita Raj
(Institute for Plasma Research)
26/10/2018, 14:00
Piero MARTIN
(Consorzio RFX)
26/10/2018, 14:00
The Divertor Tokamak Test Facility (DTT) is a new tokamak whose
construction has recently been approved by the Italian government. DTT
will be a high field superconducting toroidal device (6 T) carrying
plasma current up to 6 MA in pulses with length up to 100s, with an
up-down symmetrical D-shape defined by major radius R=2.10 m, minor
radius a=0.65 m and average triangularity 0.3. The main...
Dr
Olaf Grulke
(MPI for Plasma Physics)
26/10/2018, 14:00
Poster
A primary goal of Wendelstein 7-X (W7-X) operation is to demonstrate stationary, long pulse discharges at fusion-relevant plasma densities and temperatures. Studies on the behavior and the control of impurity ions originating from plasma-wall-interaction with the divertor and other plasma facing components is a crucial issue potentially leading to a thermal collapse and dilution of the fuel....
Dr
Andreas Dinklage
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Poster
Plasma termination by excess fuelling or impurity interaction is a safety relevant event in potential fusion reactors. Sudden termination of plasma operation is an aspect that enters material requirements in terms of released energies, localization and respective time-scales of the plasma terminating event. In tokamaks, such events may lead to disruptions or thermal quenches. While disruptions...
Dr
Fulvio Militello
(Culham Centre for Fusion Energy)
26/10/2018, 14:00
Dr
Eric M. Bass
(University of California San Diego)
26/10/2018, 14:00
Dr
Apiwat Wisitsorasak
(King Mongkut's University of Technology Thonburi)
26/10/2018, 14:00
Poster
Core-Edge simulations of the low confinement mode (L-mode) plasma are carried out using 1.5D BALDUR integrated predictive modeling code in. In each simulation, the plasma current, temperatures, and density profiles for both core and SOL regions are self-consistently evolved. The plasma profiles in the SOL region are simulated by integrating the fluid equations, including sources, along and...
Dr
Jozef ONGENA
(Plasma Physics Lab, ERM-KMS, Brussels)
26/10/2018, 14:00
Poster
An important aim of W7-X is to demonstrate fast ion confinement at volume averaged beta values up to 5% for which W7-X was optimised [1]. These high beta values correspond to plasma densities above 10^{20}m^{-3}. Mimicking the behaviour of alpha particles in a future stellarator requires the presence of energetic ions with energies in the range ~100 keV in the core of W7-X high density plasmas...
Dr
Aaro Jaervinen
(Lawrence Livermore National Laboratory)
26/10/2018, 14:00
Mr
David Rittich
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Poster
The neutral beam (NB) driven current, like the other intrinsic and driven current contributions to the total plasma current, is not directly measurable. Therefore, two strategies are used to investigate neutral beam current drive (NBCD). First, for quantitative investigations of the total NB driven current the measured total plasma current is compared with the sum of the calculated...
Markus Weiland
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Dr
Yevgen Kazakov
(Laboratory for Plasma Physics, LPP-ERM/KMS)
26/10/2018, 14:00
Lorenzo Frassinetti
(KTH, Royal Institute of Technology)
26/10/2018, 14:00
Poster
The role of the pedestal pressure position ($p_e^{pos}$) in the pedestal stability has been recently highlighted in deuterium (D) plasmas in AUG [1], where it was shown that an outward shift of the pressure can lead to a reduction in pedestal pressure height ($p^{ped}$). The work emphasized the role of scrape-off layer conditions and possibly separatrix density ($n_e^{sep}$) in the global...
Mr
RAJNISH KUMAR
(Scientific Officer-F)
26/10/2018, 14:00
Ion Cyclotron Heating and Current Drive (ICH&CD) system is one of the important auxiliary heating and current drive systems for ITER experiment [1]. Total 20 MW of IC power is required to couple with ITER plasmas using 8 independent RF sources (35-65MHz) having power handling capability of 2.5 MW at VSWR of 2:1 with other stringent specifications. To finalise the source configuration, an R&D...
Dr
Gergo Pokol
(NTI, Budapest University of Technology and Economics, Hungary)
26/10/2018, 14:00
Poster
Relativistic runaway electrons are of major concern in tokamaks. Some nice tools have been developed in the recent decades, but we still miss a self-consistent simulation tool that could simultaneously capture all aspects of this phenomenon. The EUROfusion Code Development for integrated modelling project (WPCD) facilitates integration of different plasma simulation tools this by providing an...
Dr
Valentin Igochine
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Poster
Tearing mode formation after internal crash events like sawteeth or fishbones is one of the most important MHD processes that result in a big island structure and associated confinement degradation in tokamaks. This type of tearing mode formation is considered to be the most important for future fusion reactors like ITER, because large internal events provide strong magnetic perturbations and...
Ms
Renu Bahl
(Institute For Plasma Research,)
26/10/2018, 14:00
A 60 MHz Rod type Radio Frequency Quadrupole Accelerator has been designed for material studies through Ion Irradiation at Institute For Plasma Research, Gandhinagar. Ion Irradiation has been preferred for characterization of fusion research material properties due to its inherited advantages of 1) absence of high residual radioactivity 2) well defined energy, dose rate and temperature values...
Dr
Indranil Bandyopadhyay
(ITER-India, Institute for Plasma Research)
26/10/2018, 14:00
Poster
Plasma Major Disruptions (MDs), Vertical Displacement Events (VDEs) and associated runaway electron currents in ITER are a major cause of concern in ITER operations. Major R&Ds, both experimental and well as through theory and modeling is underway across the fusion community to understand these events and find suitable amelioration techniques. In the past we have presented detailed predictive...
Dr
Nicola Vianello
(Consorzio RFX, Padova, Italy)
26/10/2018, 14:00
Poster
Addressing the role of Scrape Off Layer filamentary transport is a subject of intense studies in fusion science. Intermittent structures dominate transport in L-Mode and strongly contribute to particle and energy losses in H-mode. The role of convective radial losses has become even more important due to its contribution to the shoulder formation in L-Mode, describing the progressive...
Dr
Rudolf Brakel
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
26/10/2018, 14:00
Poster
Wall conditioning in fusion devices is prerequisite to provide controlled boundary conditions for operation and to achieve high performance plasmas. Major issues are to achieve low outgassing, low particle recycling and a low impurity level. Implementation and optimisation of a systematic wall conditioning strategy was a major issue during the second operation campaign at the superconducting...
537.
Studies of the gas puff effect on edge plasma of Aditya tokamak using coupled DEGAS2-UEDGE code
Dr
Ritu Dey
(Institute for Plasma Research)
26/10/2018, 14:00
Poster
Fuel neutral penetration and dynamics in the edge and scrape of layer (SOL) plasma region of tokamaks shape the plasma properties in these regions which play an important role in determining the core plasma confinement. Experiments in Aditya and Aditya-U tokamaks have shown that fuelling by periodic multiple gas puffs led to improved core plasma properties [1]. These experimental results...
Mr
Kedar S BHOPE
(Institute for Plasma Research , BHAT, Gandhinagar, -382428,Gujarat,INDIA), Mr
Ramesh Kumar B Buddu
(Institute for Plasma Research , BHAT, Gandhinagar, -382428,Gujarat,INDIA)
26/10/2018, 14:00
Fusion reactor components manufacturing is mainly deals with Austenitic stainless steels with different type welding techniques and kind of weld structure joints. Thick steel like 40 mm & 60 mm plates are used mainly in the fabrication of vacuum vessel, divertor and other supporting structures with different weld joining techniques like Tungsten Inert Gas (TIG) welding, Narrow Groove TIG...
Dr
Maxim Umansky
(Lawrence Livermore National Lab)
26/10/2018, 14:00
Prof.
Ambrogio Fasoli
(EPFL Swiss Plasma Center)
26/10/2018, 14:00
The range and the reactor relevance of the TCV experiments are being enhanced by two sets of major upgrades. The first set includes the installation of neutral beam injection (NBI) and new Electron Cyclotron (EC) power sources, to heat the ions and vary the electron to ion temperature ratio, in plasmas with ITER relevant β values. A 15-30keV, 1MW, 2s tangential NBI system is operational on TCV...
Dr
Braj Kishore Shukla
(Institute for Plasma Research)
26/10/2018, 14:00
The Gyrotron based electron Cyclotron resonance Heating (ECRH) system is used on tokamaks Aditya-U and SST-1. The ECRH system consists of High power Gyrotron, corrugated waveguide based transmission line and a quasi-optical launcher.
The 42GHz Gyrotron delivers 500kW power for 500ms duration. This Gyrotron operates at ~ - 48kV beam voltage and +18kV anode voltage. This system draws around 20A...
Prof.
Yongkyoon In
(Ulsan National Institute of Science and Technology)
26/10/2018, 14:00
Dr
Shaocheng Liu
(Institute of Plasma Physics Chinese Academy of Sciences)
26/10/2018, 14:00
Poster
Wendelstein 7-X (W7-X) was operated successfully with the first divertor plasma in the operation phase 1.2a (OP1.2a). A new combined probe head, which consists of Langmuir probe pins, Mach probe, ion sensitive probe (ISP), differential coil and a tri-axial pick-up coil, is able to measure the edge plasma profiles (T$_e$,n$_e$,ϕ$_f$,M$_∥$), magnetic field, poloidal and radial turbulence...
Dr
Thomas Pütterich
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 14:00
Poster
At ASDEX Upgrade experiments have been performed, in which important features of the ITER baseline (ITER BL) scenario are matched or imitated. A crucial property of the ITER BL scenario is the combination of $q_{95}=3$ with strong plasma shaping, which leads to ELM frequencies ($f_{ELM}$) as low as 10Hz, while the ELMs are very large.
One consequence of the low $f_{ELM}$ is that access to...
Richard Majeski
(Princeton Plasma Physics Lab)
26/10/2018, 14:00
Poster
The research program for LTX-beta, the upgrade to the Lithium Tokamak Experiment, combines lithium walls to produce gradient-free temperature profiles and stabilize ion and electron temperature gradient-driven modes, with approaches to stabilization of density gradient-driven modes, such as the trapped electron mode (TEM). Candidate stabilization mechanisms for the TEM include sheared flow...
Dr
R.W. (Bob) Harvey
(UsCompX)
26/10/2018, 14:00
Poster
The runaway electron distributions driven by a large toroidal electric field Etor induced by the drop in the temperature profile due to disruption or pellets are comprehensively simulated by the 3D Fokker-Planck solver CQL3D [1], recently coupled to the Ampere-Faraday (A-F) equations. The evolution of the toroidal current in a plasma occurs on a resistive time scale tr, which is typically of...
Dr
Eric M. Bass
(University of California San Diego)
26/10/2018, 14:20
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Oral
We present predictions of the ITER fusion-alpha and neutral-beam-injection (NBI) ion density and power-deposition profiles using a stiff transport critical gradient model (CGM) for Alfvén eigenmode (AE) transport in various ITER scenarios. In a burning plasma such as planned in ITER, deposited heat from fusion-born 3.5 MeV alpha particles provides most of the power needed to sustain fusion....
Dr
Timothy C. Luce
(ITER Organization)
26/10/2018, 14:40
PPC - Plasma Overall Performance and Control
Oral
Stable and robust ITER Baseline Scenario demonstration discharges have been achieved in DIII-D at zero injected input torque (matching the ITER LSN shape including the aspect ratio, betaN=1.9-2.05, and q95=3), and repeated under various conditions (Ip, density, wall conditions). However, an alternate route to Q=10 conditions has been explored that starts at higher q95 and maximum BT....
Markus Weiland
(Max-Planck-Institut für Plasmaphysik)
26/10/2018, 15:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Oral
Knowledge of the fast-ion distribution arising from neutral beam injection (NBI) is important for transport analysis and magnetic equilibrium reconstruction. For sophisticated plasma control, which will be essential for the success of future fusion devices, it is very beneficial to know this distribution function already in real-time during the discharge. Then, the relevant quantities (e.g....
Dr
Yevgen Kazakov
(Laboratory for Plasma Physics, LPP-ERM/KMS, Brussels, Belgium)
26/10/2018, 15:20
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
This contribution summarizes recent theoretical and experimental developments of a novel 'three-ion species' heating scheme that have opened new promising avenues for the application of ICRF in fusion plasmas. Following successful proof-of-principle demonstration on the Alcator C-Mod and JET tokamaks [1], this scenario has also been recently established on AUG. A small amount of 3He ions (~1%...
Dr
Gregory Wallace
(MIT Plasma Science and Fusion Center)
26/10/2018, 15:40
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Oral
We present new experimental measurements of the Lower Hybrid (LH) wave electric field vector, $E_{LH}$, obtained in Alcator C-Mod and provide a direct comparison with 3D full-wave COMSOL simulations using the cold plasma dielectric tensor and reflectometry measured density profiles. Two key results are reported: 1) The direction of $E_{LH}$ was found to have a substantial poloidal component...
Prof.
Thomas Sunn Pedersen
(Max Planck Institute for Plasma Physics)
26/10/2018, 16:40
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Wendelstein 7-X (W7-X) went successfully into operation in 2015 [1-4]. With a 30 cubic meter volume, a superconducting coil system operating at 2.5 T, and steady-state heating capability of up to 10 MW, it was built to demonstrate the benefits of optimized stellarators at parameters approaching those of a fusion power plant. Operation phase 1.2a (OP1.2a), which was performed in the second half...
Dr
Florian Effenberg
(Department of Engineering Physics, University of Wisconsin - Madison)
26/10/2018, 17:00
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Effective power exhaust by impurity seeding and its dependence on the gas species used was demonstrated in island divertor configurations for the first time at Wendelstein 7-X (W7-X).
A systematic set of experiments has been conducted during the first island divertor campaign which show that switching from Neon (Ne) to nitrogen (N2) as seeding gases enables switching from global to more...
Dr
Aaro Jaervinen
(Lawrence Livermore National Laboratory)
26/10/2018, 17:20
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
Understanding of divertor heat load and its control in fusion reactors has been critically advanced in DIII-D radiative power exhaust experiments corroborated with state-of-the-art 2D fluid simulations. UEDGE simulations indicate that the non-linear interaction between the divertor electron temperatures and drifts can drive a bifurcation of the divertor solution between attached and detached...
Prof.
Fulvio Militello
(Culham Centre for Fusion Energy)
26/10/2018, 17:40
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
This paper discusses a statistical framework that relates the fundamental physics of Scrape-Off Layer (SOL) L-mode and inter-ELM filaments with the profiles they generate in magnetic confinement devices. This work reviews the theoretical and numerical work recently carried out at CCFE in support of the statistical framework and compares it with experimental measurements obtained with...
Dr
Maxim Umansky
(Lawrence Livermore National Lab)
26/10/2018, 18:00
THD - Magnetic Confinement Theory and Modelling: Plasma–material interactions; divertors, limiters, SOL
Oral
Passively-stable fully detached divertor regimes have been found in numerical modeling of divertor configurations with radially or vertically extended, tightly baffled, outer divertor legs, with or without a secondary X-point in the leg volume [1]. Simulations carried out with the tokamak edge transport code UEDGE [2] using the base parameters of the ADX tokamak design [3] show that...
Dr
Sebastijan Brezinsek
(Forschungszentrum Jülich)
26/10/2018, 18:20
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Oral
W is the plasma-facing material of the JET-ILW divertor. W erosion by plasma and impurity impact determines the components lifetime as well as can influence the plasma performance by the W influx into the confined region. Certainly, the W screening by the divertor and the W transport into the plasma determines the W core content, but the W source itself impacts the process. Its quantification...
Dr
Katsumi Ida
(National Institute for Fusion Science)
27/10/2018, 08:30
Isotope effects of the ion particle transport both for carbon impurity and bulk ions are investigated in Large Helical Device (LHD) in a condition decoupled from electron particle transport. Better particle confinement for both impurity and bulk ions are observed in deuterium plasmas than in hydrogen plasmas. The following findings are presented in this paper. 1) Carbon impurity density...
Dr
Vladimir Vershkov
(NRC "Kurchatov institute")
27/10/2018, 08:50
Previous correlation reflectometry investigations in T-10 tokamak revealed the existence of several density fluctuation types and strong radial and poloidal variation of their amplitudes and correlation properties. This paper presents the new measurements of the 3D spatial distributions of the amplitudes, radial correlation lengths and long range correlations along the field lines of the...
Dr
Jae-Min Kwon
(National Fusion Research Institute)
27/10/2018, 09:10
We perform gyrokinetic simulations to study the effects of a stationary magnetic island on neoclassical and turbulence physics. A KSTAR L-plasma condition is employed for the simulations. Through the simulations, we aim to understand the underlying physical mechanisms of poloidal flows and fluctuations around a stationary (2,1) magnetic island, which were observed in a recent KSTAR experiment...
Mr
Pablo Rodriguez-Fernandez
(UsPSFC)
27/10/2018, 09:30
This work demonstrates that cold-pulse phenomena in tokamak plasmas can be fully explained by local transport models [1], including the existence of core temperature inversions at low density and disappearance at high density, thus resolving an enigmatic but universal transient transport phenomenon that has challenged the standard local model of transport for more than twenty years [2]. The...
Mr
Alexey Altukhov
(Ioffe Institute)
27/10/2018, 09:50
The fast linear (Born approximation) version of the X-mode Doppler reflectometry (DR) synthetic diagnostics is developed in the framework of the ELMFIRE global gyrokinetic modeling of the FT-2 tokamak ohmic discharge. The DR signal frequency spectra and the dependence of their frequency shift and shape on the probing antenna position are computed and shown to be similar to those measured in...
Ms
Harshita Raj
(Institute for Plasma Research)
27/10/2018, 10:45
EXS - Magnetic Confinement Experiments: Stability
Oral
Tearing modes play pivotal role in determining two of the most critical parameters for tokamak operation, namely plasma confinement and disruption. They have been extensively studied both theoretically and experimentally, as controlling them is foremost priority for every tokamak, including ITER and future large size tokamaks. Coupling of tearing modes with drift wave is a common phenomenon...
Dr
Minjun J. Choi
(National Fusion Research Institute)
27/10/2018, 11:05
EXS - Magnetic Confinement Experiments: Stability
Oral
Tokamak plasmas often encounter non-axisymmetric magnetic topology due to unavoidable magnetohydrodynamic (MHD) instabilities and/or external magnetic perturbation. Transport with non-axisymmetric perturbed equilibrium can be very complicated due to various multiscale interactions between a large scale MHD instability and small scale micro instabilities. This paper reports experimental...
Prof.
satoshi konishi
(kyoto university)
27/10/2018, 11:25
SEE - Safety, Environmental and Economic Aspects of Fusion
Oral
A. This paper proposes a new and innovative fusion energy application in the emissions trading market based on the combination with biomass processing. An endothermic biomass conversion reaction of charcoal making process, or dry distillation;
(CH1.6O0.6) = C+0.4H2+0.6H2O-451kJ (where biomass is assumed to be woody including large fraction of lignin.) can convert fusion energy obtained as...
Prof.
satoshi konishi
(kyoto university)
27/10/2018, 11:35
SEE - Safety, Environmental and Economic Aspects of Fusion
Oral
The economic performance of steady-state fusion power plants on future deregulated electricity markets was quantitatively analyzed for the first time with a newly constructed Simplified PJM Market Model. The results showed that (i) discussions based on simple levelised cost of electricity are insufficient for deregulated markets and (ii) the unplanned outage frequency target should be lowered...
Prof.
Satoshi Konishi
(Kyoto University)
27/10/2018, 11:40
SEE - Safety, Environmental and Economic Aspects of Fusion
Oral
This paper aims to investigate techno-economic analysis of fusion-biomass hybrid model based on previously proposed technical and chemical concept. Fusion-biomass hybrid model, which takes no value of waste biomass from municipal, agricultural, and forestry areas as feedstock, produces synthetic gas generated by endothermic pyrolytic gasification using high temperature of fusion heat. Several...
Dr
Nicholas Eidietis
(General Atomics)
27/10/2018, 11:45
EXS - Magnetic Confinement Experiments: Stability
Post Deadline
Jerome Bucalossi
(CEA)
27/10/2018, 12:05
FIP - Fusion Engineering, Integration and Power Plant Design
Post Deadline
Richard Hawryluk
(Princeton Plasma Physics Laboratory),
Sophia Le Masurier
27/10/2018, 14:00
Dr
David Campbell
(ITER Organization)
27/10/2018, 14:30
Dr
Katsumi Ida
(National Institute for Fusion Science (NIFS), Toki, Gifu, Japan)
27/10/2018, 15:00
Prof.
Ricardo Galvao
(University of Sao Paulo)
27/10/2018, 15:30
Bahukutumbi P. Radha
(University of Rochester)
27/10/2018, 16:30
Dr
Takashi Inoue
(JAEA Naka)
27/10/2018, 17:00
