Ms
MEERA VENKATESH
(INTERNATIONAL ATOMIC ENERGY AGENCY)
10/22/18, 8:35 AM
Host Country Representative
(India)
10/22/18, 8:45 AM
Ravi B. Grover
(Homi Bhabha National Institute (HBNI), Anushakti Nagar, Mumbai 400094, India)
10/22/18, 9:00 AM
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)
10/22/18, 9:30 AM
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)
10/22/18, 9:50 AM
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)
10/22/18, 10:45 AM
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)
10/22/18, 11:10 AM
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)
10/22/18, 11:35 AM
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)
10/22/18, 12:00 PM
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)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
Dr
Stanislas Pamela
(CCFE - UKAEA)
10/22/18, 2:00 PM
Edward Strait
(General Atomics)
10/22/18, 2:00 PM
Hiroshi Gota
(TAE Technologies, Inc.)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
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
10/22/18, 2:00 PM
Bahukutumbi P. Radha
(University of Rochester)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
Mr
Min Xu
(Southwestern Institute of Physics)
10/22/18, 2:00 PM
Dr
James Harrison
(CCFE)
10/22/18, 2:00 PM
Mr
Rakesh Tanna
(Institute For Plasma Research)
10/22/18, 2:00 PM
Dr
Hendrik Meyer
(UK Atomic Energy Authority)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
Dr
Earl Marmar
(Mass. Inst. of Technology)
10/22/18, 2:00 PM
Dr
Tomohiro Morisaki
(National Institute for Fusion Science)
10/22/18, 2:00 PM
Dr
Gianluca Pucella
(ENEA)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
Prof.
Hyeon K. Park
(UNIST)
10/22/18, 2:00 PM
Dr
Nengchao Wang
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (IFPP), AEET, SEEE, CnHUST)
10/22/18, 2:00 PM
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)
10/22/18, 2:00 PM
Dr
Enrique Ascasibar
(CIEMAT)
10/22/18, 2:00 PM
Dr
Stefano Coda
(CRPP-EPFL)
10/22/18, 2:00 PM
Dr
John Kline
(LANL)
10/22/18, 2:00 PM
Arun Kumar Chakraborty
(ITER-India, Institute for Plasma Research)
10/22/18, 2:00 PM
pietro barabaschi
(f4e)
10/22/18, 2:00 PM
Dr
Guoqiang Li
10/22/18, 2:00 PM
Mr
Bernard Bigot
(ITER Organization)
10/22/18, 2:00 PM
Dr
Baonian Wan
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/22/18, 2:00 PM
Dr
Hiroyasu Tanigawa
(Japan Atomic Energy Agency)
10/22/18, 2:00 PM
Mr
Nikolai Bakharev
(Ioffe Institute)
10/22/18, 2:00 PM
Dr
Baonian Wan
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/22/18, 2:25 PM
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)
10/22/18, 2:50 PM
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)
10/22/18, 3:15 PM
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)
10/22/18, 4:40 PM
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)
10/22/18, 5:00 PM
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)
10/22/18, 5:10 PM
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)
10/22/18, 5:15 PM
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))
10/22/18, 5:20 PM
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))
10/22/18, 5:30 PM
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))
10/22/18, 5:35 PM
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)
10/22/18, 5:40 PM
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)
10/22/18, 6:00 PM
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)
10/22/18, 6:20 PM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Dr
Hiroyuki Tobari
(National Institute of Quantum and Radiological Science and Technology)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Ms
Elizabeth Tolman
(UsPSFC)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Mr
Atsushi Kojima
(National Institutes for Quantum and Radiological Science and Technology)
10/23/18, 8:30 AM
Poster
Mr
Himanshu Tyagi
(ITER-India,IPR)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Mr
Alexey Razdobarin
(Ioffe Institute)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Mr
Henri Weisen
(SPC EPFL)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Dr
Sergei Gerasimov
(CCFE)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Dr
Paritosh Chaudhuri
(Institute for Plasma Research)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
Poster
Mr
John Smith
(General Atomics)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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.)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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))
10/23/18, 8:30 AM
Poster
Mr
Alexey Vertkov
(SC "Red Star")
10/23/18, 8:30 AM
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
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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”)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:30 AM
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)
10/23/18, 8:55 AM
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)
10/23/18, 9:20 AM
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)
10/23/18, 9:45 AM
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)
10/23/18, 10:45 AM
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)
10/23/18, 11:05 AM
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)
10/23/18, 11:25 AM
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)
10/23/18, 11:45 AM
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)
10/23/18, 12:05 PM
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)
10/23/18, 12:15 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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))
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Mr
Shrishail Padasalagi
(ITER-India, IPR, HBNI)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Dr
Pengjun Sun
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Mr
Prabhakar Srivastav
(Institute For Plasma Research, Bhat Gandhinagar India-382428)
10/23/18, 2:00 PM
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
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Dr
Alessandro Biancalani
(Max-Planck-Institut für Plasmaphysik)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Dr
Yurii V. Yakovenko
(Kyiv Institute for Nuclear Research, Kyiv, Ukraine)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
Poster
Mr
Antti Snicker
(Aalto University)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:00 PM
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)
10/23/18, 2:25 PM
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)
10/23/18, 2:50 PM
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)
10/23/18, 3:15 PM
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)
10/23/18, 3:40 PM
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)
10/23/18, 5:05 PM
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)
10/23/18, 5:30 PM
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)
10/23/18, 5:55 PM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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"))
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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))
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:30 AM
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)
10/24/18, 8:50 AM
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)
10/24/18, 9:10 AM
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)
10/24/18, 9:30 AM
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)
10/24/18, 9:50 AM
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)
10/24/18, 10:45 AM
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)
10/24/18, 11:25 AM
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)
10/24/18, 11:45 AM
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)
10/24/18, 12:05 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
Poster
Mr
Amit Kumar Singh
(ITER-India, Institute for Plasma Research)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
Poster
Mr
Umesh Kumar Nagora
(Institute for Plasma Research)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
Poster
Dr
Elena de la Luna
(CIEMAT)
10/24/18, 2:00 PM
Poster
Mrs
RANJANA MANCHANDA
(INSTITUTE FOR PLASMA RESEARCH)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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
10/24/18, 2:00 PM
Poster
Mrs
sapna Mishra
(ITER-India,Institute for plasma research)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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")
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
Poster
Dr
Shinsuke Fujioka
(Institute of Laser Engineering, Osaka University)
10/24/18, 2:00 PM
Poster
Prof.
Dimitri Batani
(Université de Bordeaux)
10/24/18, 2:00 PM
Poster
Dr
Takeshi Watari
(Central Research Laboratory, Hamamatsu Photonics K.K.)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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)
10/24/18, 2:00 PM
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
10/24/18, 2:00 PM
Poster
Dr
Darin Ernst
(MIT)
10/24/18, 2:00 PM
Poster
Dr
Francesca Turco
(Columbia University)
10/24/18, 2:40 PM
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)
10/24/18, 3:20 PM
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)
10/24/18, 3:40 PM
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)
10/24/18, 4:40 PM
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)
10/24/18, 5:00 PM
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)
10/24/18, 5:20 PM
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)
10/24/18, 5:40 PM
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)
10/24/18, 6:00 PM
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)
10/25/18, 8:30 AM
Poster
Dr
paolo zanca
(consorzio rfx)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Prof.
Giuseppe Calabro
(University of Tuscia)
10/25/18, 8:30 AM
Poster
Prof.
YI LIU
(Southwestern Institute of Physics)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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')
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Dr
Toseo Moritaka
(Institue for Fusion Science)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Dr
Golo Fuchert
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
10/25/18, 8:30 AM
Poster
Mr
Maxim Nurgaliev
(National Research Centre "Kurchatov Institute")
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Dr
Francesca Turco
(Columbia University)
10/25/18, 8:30 AM
Poster
Dr
Masahiko Sato
(National Institute for Fusion Science)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Min Jiang
(Southwestern Institute of Physics)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
Poster
Dmitriy Ryzhakov
(RuKurchatov)
10/25/18, 8:30 AM
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)
10/25/18, 8:30 AM
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 streame