Dr
Subhash P.V
(ITER-India, Institute for Plasma Research, Gandhinagar, Gujarat)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Nuclear activation and subsequent radiological response of structural materials within fusion reactors like ITER and beyond need to be studied for operational, safety and radiological waste management reasons. The future fusion machines should be equipped with low radioactive materials optimized for expected neutron environment. Numerical tools with extended capabilities are needed for this...
Mr
Gheesa Lal Vyas
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Charge eXchange Recombination Spectroscopy (CXRS) diagnostic shall provide the key measurement for ITER advance plasma control and physics studies. ITER CXRS-pedestal has a primary role of edge ion temperature, plasma rotation (toroidal and poloidal velocity) and impurity density measurements in the pedestal region (r/a=0.85 -1.0). Meeting the measurement requirements for these parameters in...
Mr
VENKATA NAGARAJU MUVVALA
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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,...
Dr
Stefan Simrock
(ITER)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER requires extensive diagnostics to meet the demands for machine operation, plasma control, protection, safety and physics studies. Most diagnostics require high performance scientific computing for the processing of complex algorithms for the measurements. The most stringent requirements are found in the more than 50 diagnostics measurement systems in terms of high performance data...
Mr
Kaushal Patel
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In tokamaks, baking of vacuum vessel and first wall components is a prerequisite in order to obtain impurity free plasmas. Baking is performed to remove impurities viz. H2, H2O and Hydro-Carbon from the vessel and first wall components. ADITYA tokamak has been upgraded ADITYA-U tokamak to achieve shaped plasmas. The ADITYA-U is equipped with a comprehensive baking system for heating the SS...
Dr
Ivo Furno
(EPFL- CRPP)
23/10/2018, 08:30
Poster
The fundamental interactions between turbulent structures or blobs and suprathermal ions, injected by Li6+ beams in plasmas created by microwaves at 2.45GHz with ne~1015-1017m-3 and Te~2-10eV, are extensively investigated on the TORPEX toroidal device. Comparisons between fully validated numerical simulations and experimental 3D time-averaged suprathermal ion profiles reveal an entire spectrum...
Dr
Li Li
(Donghua University, Shanghai, China)
23/10/2018, 08:30
Poster
The plasma response to the 3-D external resonant magnetic perturbation (RMP) fields, applied for controlling type-I edge localized modes (ELMs) in ITER, is systematically computed in terms of the normal displacement of the plasma surface, in other words the 3-D corrugation of the plasma boundary. Five representative ITER H-mode plasma scenarios, ranging from an initial hydrogen plasma...
Dr
Hiroyuki Tobari
(National Institute of Quantum and Radiological Science and Technology)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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...
Ms
Elizabeth Tolman
(UsPSFC)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ARC pilot plant conceptual design study [1] is extended to explore options for managing ~525 MW of fusion power generated in a compact high field ($B_0$ = 9.2 T) tokamak about the size of JET ($R_0$ = 3.3 m). Exploiting ARC’s demountable high temperature superconductor toroidal field (TF) magnets, poloidal magnetic field (PF) coils located inside the TF, and vacuum vessel (VV) immersed in...
Dr
Elena Gaio
(Consorzio RFX)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The JT-60SA satellite tokamak is now under advanced assembly phase in Naka (Japan). The majority of the new power supplies are provided by Europe, and the Italian National Research Council (CNR), acting through Consorzio RFX, has contributed in particular with two systems: the Quench Protection Circuits (QPC) for the superconducting magnets and the Power Supply System for RWM control.
The...
Mengdi Kong
(ChSPC)
23/10/2018, 08:30
Poster
Detailed experiments have been performed on TCV with its flexible electron cyclotron heating/current drive system to investigate reliable and efficient control of NTMs. For example, a novel sinusoidal sweeping technique has been studied in detail and we have shown for the first time that it is efficient for both NTM stabilization and preemption. This method is important for future devices as...
Mr
ASHOK MANKANI
(IPR)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
At IPR Neutral Beam Injection (NBI) facility to heat and drive the plasma current in Tokamak is been built by accelerating the positive / negative ion beam of energy around 100 keV. Under the current R&D plan the projection is to develop the technology for future Mega Volt range DC Power Source facility to accelerate ion beam of energy to the tune of 1 MeV and power of the order of few MW. To...
Mr
Himanshu Tyagi
(ITER-India,IPR)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Indian Test Facility (IN-TF) [1] is being built in IPR to characterize Diagnostic Neutral Beam [2] in cooperation with ITER Organization. INTF is a complex system which consists of several plant systems like beam source, gas feed, vacuum, cryogenics and mechanical systems. To ensure successful operation INTF, integrated operation involving all the constituent plant systems is required. The...
Mr
Krishan Kumar Gotewal
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Remote Handling (RH) systems for maintenance and inspection of in-vessel components have been addressed in great detail for fusion machines around the world. Maintaining high availability of fusion machine and minimizing the maintenance time require robust and dependable RH systems. Such RH systems, being electro-mechanical in nature, requires research and development in various areas such as...
Mr
SIDDHARTH KUMAR
(ITER INDIA)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the ITER, systems are classified in the different safety categories as per their function in the machine; Protection Important Components (PIC) needs more attention during the design and analysis for better safety margins. The French Nuclear Code RCC-MR (2007) is employed in the design, analysis and the manufacturing, applicable to the ITER protection important mechanical components. It is...
Dr
Anil Tyagi
(ITER-India, Institute for Plasma Research), Mr
Matteo Barbarino
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Tungsten (W) will be used in ITER as a Plasma Facing Material (PFM) in divertor due to its capability to handle high heat flux while having a low Hydrogen (H) isotope affinity. However in presence of fusion neutrons and alpha particles, tungsten can accumulate radiation damage, which might significantly enhance its H retention property. In order to investigate the effects of radiation damage...
Mr
RAVINDER KUMAR
(ITER-INDIA,INSTITUTE FOR PLASMA RESEARCH)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
For ITER Electron Cyclotron Emission (ECE) diagnostic, there is a requirement of high-temperature black body radiation source operating at atmospheric pressure. This source needs to be operated at high temperature (~ 500 0C) having a microwave emissivity > 0.95 in the frequency band 100-500 GHz, and > 0.75 for 500-1000 GHz. Moreover, the radiation surface should have temperature uniformity...
Dr
Tsuyoshi Kariya
(Plasma Research Center, University of Tsukuba)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Megawatt (MW) gyrotrons with a wide frequency range from 14 to 300 GHz are being developed in a collaborative ECH study for advanced fusion devices and a DEMO. (1) Detailed designs of a 14 GHz 1 MW gyrotron has been started for actual fabrication. For a 14 GHz RF beam with high divergence, a calculated transmission efficiency of 85% to the corrugated waveguide coupling position was initially...
Dr
Ryota Imazawa
(National Institutes for Quantun and Radiological Science and Technology)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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...
Mr
Alexey Razdobarin
(Ioffe Institute)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The performance of front-end elements of optical diagnostics in ITER under long-term operation and with limited access for their maintenance is in the focus of extensive R&D program involving laboratory study and testing in working tokamaks. The requirements to the front-end element design are driven by high-energy neutron and gamma radiation, intense particle fluxes and thermal loads at the...
Dr
Michael Komm
(Institute of Plasma Physics of the Czech Academy of Sciences)
23/10/2018, 08:30
Poster
Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and next–step devices, as it allows to convert the majority of the energy carried by charged particles through the scrape-off-layer (SOL) into isotropic radiation and thus avoids localized heat flux deposition in the divertor region. In order to maintain relevance to ITER and DEMO, a concentrated effort...
Mr
SRINIVASA MURALIDHARA
(ITER-INDIA)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Auxiliary Cold Boxes (ACBs) of the ITER cryodistribution system has multiple cryogenic process volumes as well as interfaces with cryolines with isolated vacuum spaces. The cryogenic process volumes inside a single vacuum space have different temperature level, 4 K and 80 K as well as different operating pressure, 0.5 MPa and 1.8 MPa. The cryogenic process volumes including interfacing...
Dr
Carlo Sozzi
(Istituto di Fisica del Plasma - CNR, Milano, Italy)
23/10/2018, 08:30
Poster
Disruption prevention in the perspective of high performance, high current, long duration plasma discharges requires a substantial evolution of the schemes applied in most of the present tokamaks. An efficient prevention scheme requires the early identification of the nature of the off-normal behavior possibly leading to a disruption and the automatic selection of the appropriated...
Dr
Shinsuke Satake
(National Institute for Fusion Science, Japan)
23/10/2018, 08:30
Poster
The effect of magnetic perturbations on the rotation profile in tokamak has been studied both experimentally and theoretically, since the prediction and control of the plasma rotation is one of the key issues for the stable operation. The NTV torque caused by magnetic perturbations is evaluated by adopting either a local or global drift-kinetic models. In the local models, the finiteness of...
Dr
Jonathan Menard
(Princeton Plasma Physics Laboratory)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Electromagnetic Particle Injector (EPI) has the potential for delivering the radiative payload to the plasma center on a 3-4 ms time scale, much faster, and deeper, than what can be achieved using present methods. Predicting and controlling disruptions is an important and urgent issue for ITER. While a primary focus is the early prediction and avoidance of conditions favorable to a...
Dr
Matej Mayer
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
Poster
During JET operation with all carbon walls prior to 2010 (JET-C) massive re-deposition of previously eroded carbon was observed in the divertor and in remote divertor areas. This massive carbon re-deposition was accompanied by a high retention of hydrogen isotopes trapped by co-deposition. Extrapolations of these results to ITER predicted very high potential tritium retention, resulting in the...
Dr
Masahiro Tanaka
(National Institute for Fusion Science)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The control and management of tritium in a fusion test facility is one of the important issues from the viewpoints of radiation safety and public acceptance. As for the tritium control in a fusion test device, understanding of tritium behavior in the exhaust gas would give us new knowledge into the characteristics of the tritium release and inventory. In the deuterium plasma experiment on the...
Mr
Nitin Bairagi
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The SST-1 cryostat houses 130 thermal shields cooled using liquid nitrogen, 16 toroidal field (TF) coils, 9 poloidal field (PF) coils and their associated support structures. Superconducting Magnets System (SCMS) of the SST-1 consisting of TF and PF coils is designed to cool with forced flow supercritical helium (SHe) at 4 bar (a), 4.5 K and a mass flow rate of 300 g/s using helium...
Dr
Matthew John Hole
(Australian National University)
23/10/2018, 08:30
Poster
In general, the operation of AC discharges in small tokamaks requires the control of a few external parameters such as vertical and horizontal fields, external heating (where available), chamber conditioning and gas puff. The dynamics and type of control used are mostly based on experimental empirical learning, with different combinations of actuators depending on the tokamak device....
Dr
Katsunori Ikeda
(JpNIFS)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Deuterium beam operation of the negative-ion-based neutral beam injector (N-NBI) was initiated in the Large Helical Device (LHD) in 2017. Both hydrogen (H) and deuterium (D) neutral beams were generated by changing the operation gas using the same accelerator. Comparison of the beam properties such as the extracted negative ion current and the co-extracted electron current, obtained with $\rm...
Dr
Chiara Piron
(ItRFX)
23/10/2018, 08:30
Poster
The fully non-inductive sustainment (“V_loop~0") of high normalized beta (“β_N”) plasmas is a crucial challenge for the steady-state operation of a tokamak reactor. In order to assess the difficulties associated with such scenarios, steady-state regimes have been explored on TCV using the newly available 1MW Neutral Beam Injection (NBI) system. Compared to the past [O. Sauter et al Phys. Rev....
Dr
Dmitriy Borodin
(Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung IEK-4: Plasmaphysik)
23/10/2018, 08:30
Poster
Beryllium (Be) erosion data is one of the key issues for ITER including the first wall (FW) life time predictions [1], which undergo a re-visit based on the recent studies at the existing devices: tokamak JET equipped with the ITER-like wall (ILW) and linear plasma device PISCES-B. The extrapolation of physical and chemically assisted sputtering data is based on interpretive and predictive...
Mr
Stefan Jachmich
(BeLPP)
23/10/2018, 08:30
Poster
Metallic first mirrors are essential plasma-facing components (PFC) in all optical spectroscopy and imaging systems used for plasma diagnosis. First Mirror Test (FMT) has been carried out at the JET tokamak with the ITER-like wall (JET-ILW). Over 120 test Mo mirrors were exposed in JET during the entire project. The aim is to provide an overview of results obtained for mirrors exposed during:...
Dr
Hyun-Tae Kim
(EUROfusion Consortium JET)
23/10/2018, 08:30
Poster
This paper presents the transport analysis of high density baseline discharges in the 2016 experimental campaign of the Joint European Torus with the ITER-Like Wall (JET-ILW), where a significant increase in the Deuterium-Deuterium (D-D) fusion neutron rate (~2.8 x 1016 sec-1) was achieved with stable high Neutral Beam Injection (NBI) powers of up to 28MW and low gas puffing.
Increase in...
Dr
Zhehui Wang
(Los Alamos National Laboratory)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Motivated by edge localized mode (ELM) control in H-mode plasmas, we summarize experimental and theoretical progress in MHD physics of plasma interaction with small pellets ranging from 10s of microns to a few mm in size. Layered spherical structures with a hollow core (“hollow pellets”) are attractive in comparison with solid spheres and gas puffing. Theoretical results based on multi-fluid...
Dr
Domenico Frigione
(ENEA)
23/10/2018, 08:30
Poster
Impact of low-mid Z impurity injection on plasma transport and confinement has been observed and reported in several Tokamak experiments. Understanding particle transport in mixed species plasmas is crucial for reactor relevant conditions where control of DT mixture along with control of He concentration will be necessary. In this paper we present the analysis of experimental electron density...
Dr
Ken Kajiwara
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
This report describes the key development of the ITER equatorial ECH/ECCD launcher (EL) for poloidal steering compatibility. The steering direction of the EL has been changed from toroidal to poloidal in order to enhance the current drive capability. The design modification is being progressed toward the design finalization in 2019.
The concept of upper launcher (UL) steering mechanism of...
Mr
Manoahstephen Manuelraj
(Institute for Plasma Research, Gandhinagar, Gujarat-382428, INDIA)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The plasma facing components (PFCs) in a tokamak are subjected to high heat flux and high temperature during plasma operation, which causes erosion of the first wall. There is also hot spot formation on the PFC due to physical phenomenon like thermal electron emission. In addition to fore-mentioned phenomenon, the events such as Edge Localized Mode (ELM), vertical displacement event (VDE) are...
Prof.
Igor Garkusha
(NSC KIPT)
23/10/2018, 08:30
Poster
Features of plasma energy transfer to the material surfaces during the plasma-surface interaction in presence of strong magnetic field are investigated within recently developed quasi-stationary plasma accelerator QSPA-M. This novel PSI test-bed facility is able to reproduce the ELM impacts, both in terms of heat load and particle flux to the surface, and to provide plasma transportation in...
Mr
David Schwörer
(Dublin City University, Ireland)
23/10/2018, 08:30
Poster
Filaments are field aligned, non-linear density perturbations, which
have been observed in most plasmas.
In tokamaks they can
carry a significant amount of particles and heat from the last
closed flux surface to the far scrape-off layer (SOL).
This highly non diffusive transport mechanism
can cause a
significant heat load onto first wall materials. It is
important to understand
the...
Mr
Narinder Pal Singh
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Acceleration Grid Power Supplies (AGPS) provides 8MW power at (-) 96kV to the beam source of DNB (Diagnostic Neutral Beam) and SPIDER (Source for Production of Ion of Deuterium Extracted from Rf plasma) for acceleration of negative ions with specific modulation. High Voltage Power supplies (HVPS) based on PSM (Pulse Step Modulation) topology has already demonstrated its ability for broadcast...
Dr
Alexey Dnestrovskiy
(NRC Kurchatov institute)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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...
Mr
Henri Weisen
(SPC EPFL)
23/10/2018, 08:30
Poster
Heat, particle and momentum confinement in L- and H-mode in deuterium (D), hydrogen (H) and in D/H mixtures have been investigated in JET. In L-mode (3T/2.5MA) at fixed density (2.5x10^19m^-3) a weak positive scaling of stored energy with ion mass, tau_Eth~A^0.15, is found [1], consistently with multi-machine scaling tau_Eth~A^0.2 [2]. Core temperature profiles are stiff with Ti~Te, and...
Mr
Ritesh SUGANDHI
(Institute for Plasma Research, Gandhiangar, India)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Large Volume Plasma Device (LVPD) [1] is a cylindrical shaped pulsed plasma device dedicated in carrying investigations relevant to fusion and magneto-spheric plasma. For meeting requirements for its up gradation, efforts are in progress towards enhancing plasma duration (tpulse ~9-50ms), to cater need of controlled experiments on Electron Temperature Gradient(ETG) turbulence, a major...
Mr
Stefan Jachmich
(BeLPP)
23/10/2018, 08:30
Poster
The high thermal loads caused by a disruption of an ITER baseline scenario pulse potentially stored thermal energy of 350MJ and magnetic energy inside the vessel of 400 MJ pose a severe threat to the first wall components [1]. Massive gas injection (MGI) into a disrupting plasma has been shown to be capable of reducing the energy deposited onto the plasma facing components by increasing the...
Dr
Michael Drevlak
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
Poster
The ROSE code was written for the optimisation of stellarator equilibria. It
uses VMEC for the equilibrium calculation and several different optimising
algorithms for adjusting the boundary coefficients of the plasma. Some of
the most importand capabilities include optimisation for simple coils, the
ability to simultaneously optimise vacuum and finite beta field, direct
analysis of...
Mr
Deepak Aggarwal
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The tritium breeding blanket is the essential part of a fusion reactor which provides the tritium fuel self-sufficiency to the reactor. India under its breeding blanket R&D program for DEMO is focusing on the development of two breeding blanket concepts viz. Lead–Lithium cooled Ceramic Breeder (LLCB) and Helium Cooled Ceramic Breeder (HCCB). The study presented in this paper focuses on the...
Dr
Naohiro Kasuya
(Kyushu University)
23/10/2018, 08:30
Poster
Some experimental observations show poloidal asymmetry in the turbulence measurements, which can affect the plasma transport, so detailed spatial structures must be clarified. In Large Helical Device (LHD), an up-down asymmetry has been observed by the PCI diagnostic. Complicated configurations make it difficult to capture the entire structures of fluctuations in helical plasmas, so...
Dr
Carlos Hidalgo
(CIEMAT)
23/10/2018, 08:30
Poster
Turbulence spreading is the transfer of free turbulent energy from strongly driven (i.e., unstable regions) to weakly driven locations [1]. The net effect of this phenomenon is the radial redistribution of turbulent energy, modifying local plasma features. It has been pointed out that spreading may be important in setting the Scrape-Off Layer (SOL) width. The peak heat load onto the divertor...
Dr
Sergei Gerasimov
(CCFE)
23/10/2018, 08:30
Poster
This paper presents an analysis of disruptions occurring during JET-ILW plasma operations covering the period from #80128 up to #92504. The total number of disruptions was 1951 including 466 MGI (massive gas injection), VDE (vertical displacement event) and Error Field Correction Coil experiments, which led to intentional disruptions; hence the average disruption rate is 16.1%. MGI has been...
Dr
David Brower
(University of California Los Angeles)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The International Tokamak Physics Activity (ITPA) Topical Group (TG) on Diagnostics has been conducting R&D activities to support improved ITER diagnostic performance. In this paper, highlights of the Topical Group activity are overviewed: mitigation of first mirror degradation in optical systems, mirror cleaning techniques have been progressed; in-vessel stray-light has been investigated to...
Mr
Rohitkumar Panchal
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
At IPR, 1350 W at 4.5 K helium cryo plant is dedicated to facilitate the cooling requirements of SST-1 machine. Since 2004, helium refrigerator / liquefier (HRL) (Make: M/s. Air Liquide, France) is operational in mixed mode equivalent to 650 W (refrigeration power) and 200 lh-1 (liquefaction capacity) at 4.5 K. The HRL can be operated in two phase (1.3 – 1.5 bar (a) at 4.5 K – 4.7 K) as well...
Dr
Juergen Rapp
(Oak Ridge National Laboratory)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Material Plasma Exposure eXperiment (MPEX) is a planned linear plasma device to address plasma-material interactions for future fusion reactors. Its concept does foresee the capability to expose apriori neutron irradiated material samples to fusion reactor grade divertor plasmas. This new capability will be unique world-wide addressing important research needs in the area of fusion nuclear...
Dr
Sergei Sharapov
(CCFE)
23/10/2018, 08:30
Poster
A deuterium-tritium (D-T) experimental campaign DTE2 on JET scheduled for 2019-2020,will be done in the Be/W vessel and will address essential operational, technical, diagnostic and scientific issues in support of ITER [1]. In preparation for the campaign, developments were performed on JET aiming at studies of alpha-particles. For studying AEs driven entirely by alpha-particles, a scenario...
Dr
Friedrich Schluck
(DeFJ)
23/10/2018, 08:30
Poster
Present-day fusion devices are operated with a multitude of diagnostics in different locations, with which important insight in plasma profiles is obtained. However, since the detected signals only represent a spatially small part of the machine, the experiment natively exhibits blind spots, in particular in the three dimensional edge plasma region, where flux surface averaging reductions are...
Dr
Brendan Lyons
(General Atomics)
23/10/2018, 08:30
Poster
An integrated-modeling workflow has been developed to predict equilibria and response to 3D magnetic perturbations in tokamak experiments. Starting from an equilibrium reconstruction from a past experiment, the workflow couples together the EFIT Grad-Shafranov solver, EPED model for pedestal stability, and NEO drift-kinetic-equation solver (for bootstrap current calculations) in order to...
Mr
SHIVAKANT JHA
(ITER-INDIA, IPR)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In ITER, plant Instrumentation & Control (I&C) components are exposed to harsh environment. Hence I&C for plant system is one of the most challenging requirements to fulfil the ITER demands. IN DA is responsible for the delivery of several diagnostics systems including (1) X-Ray Crystal Spectroscopy (XRCS) edge & survey to measure the plasma impurity for machine protection and basic control...
Dr
Laizhong Cai
(Southwestern Institute of Physics)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
For a DEMO reactor, the first candidate material for plasma facing material(PFM) is tungsten(W) and current available structure material is reduced activation ferritic/martensitic (RAFM). And tungsten coating material is promising to be applied on first wall. Since chemical vapor deposition tungsten (CVD-W) has a higher density, less porosity and better thermal shock resistance, thick CVD-W...
Mr
Aditya Kumar Verma
(Institute For Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Experimental Helium Cooling Loop (EHCL) is a high pressure-high temperature helium gas system. EHCL is similar to the First Wall Helium Cooling System (FWHCS) of LLCB TBM and in this loop First wall mock ups up to one fourth (¼) size of TBM can be tested.
EHCL modelling consists of equipment arrangement, pipe routing, support, cable tray routing, instrumentation arrangement and tube...
Dr
HITESH KUMAR PANDYA
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ECE Diagnostic system in ITER will be used to determine the electron temperature profile evolution, the high frequency fluctuation of the plasma electron temperature, the characterization of runaway electrons and the radiated power in the electron cyclotron frequency range (70-1000 GHz). These measurements will be used for advanced real time plasma control (e.g. steering the electron...
Dr
Takayuki Kobayashi
(National Institutes for Quantum and Radiological Science and Technology)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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
Paritosh Chaudhuri
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Several materials have been developed and being investigated for reliable and sustainable breeder candidate material. Lithium meta-titanate (Li2TiO3) and Lithium ortho-silicate(Li4SiO4) are the prominent among the suitable candidate materials for breeders. India has proposed lithium meta-titanate (Li2TiO3) as the tritium breeder materials in the form of pebble bed for LLCB TBM. Li2TiO3 power...
Prof.
Mahendrajit Singh
(ITER - India Institute for Plasma Research Bhat Gandhinagar Gujarat 382428 India)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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...
Mr
John Smith
(General Atomics)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Several key milestones have been completed recently in the fabrication of the Central Solenoid (CS) modules for ITER. The qualification coil has been completed and tested with many lessons learned that have now been incorporated into the processing of the production modules. Currently four modules are in production with the first module scheduled for completion in 2018 followed by full...
Dr
Atsushi Kasugai
(Japan Agency for Quantum and Radiological Science and Technology (QST), Rokkasho Fusion Institute)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The IFMIF project aiming at material tests for a future fusion DEMO reactor is under the EVEDA phase in the BA Agreement of fusion program between Japan and EU. As the accelerator activity, the installation and commissioning of the Linear IFMIF Prototype Accelerator (LIPAc) is at the second stage of demonstration of the feasibility of the low energy section of an IFMIF deuteron accelerator up...
Mr
Ondrej Ficker
(CzIPP, CzFNSP)
23/10/2018, 08:30
Poster
Runaway electrons (REs) as one of the yet unsolved threats for ITER and future tokamaks are a topic of intensive research at most of the tokamaks. The experiments performed on COMPASS are complementary to the experiments at JET and MST (Medium-Size Tokamaks), building on the flexibility of the diagnostics set-up and low safety constraints at this smaller (R0=0.56 m, a=0.23 m) device. During...
Mr
Rohit Anand
(ITER India , IPR)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER-India is responsible for delivery of 8+1(prototype) RF sources to ITER project. Each RF source will provide 2.5MW of RF power at VSWR 2:1 in the frequency range of 35 to 65MHz. Eight such RF sources will generate total 20MW of RF power. Two RF chains containing three high power amplifiers (HPA1, HPA2 and HPA3) need to be combined to build an RF source. HPA2 and HPA3 are RF tube based...
Dr
Larry R. Baylor
(Oak Ridge National Laboratory)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The technology of forming high-Z cryogenic pellets mixed with D2 that are shattered upon injection into a plasma has been developed at ORNL for mitigating disruptions and has been selected as the basis for the baseline disruption mitigation system on ITER. In these shattered pellet injectors (SPIs), large pellets of neon and argon mixed with D2 are formed from gas and are shattered upon impact...
Dr
Basil Duval
(Ecole Polytechnique Fédérale de Lausanne – Swiss Plasma Center (SPC), Association Euratom-Confédération Suisse(EPFL) CH-1015 Lausanne, Switzerland)
23/10/2018, 08:30
Poster
This paper presents a fresh attempt on TCV to optimise plasma breakdown in the break-less (45 micro-Ohm impedance) vacuum vessel culminating in a double breakdown and the formation of a doublet configuration. A statistical analysis of legacy single pole breakdown and early plasma current ramp failures helped modify vessel current estimators together with PSU command and control issues to...
Prof.
Christian Theiler
(EPFL-SPC)
23/10/2018, 08:30
Poster
The effect of magnetic geometry on scrape-off layer (SOL) transport and detachment behavior is investigated on the TCV tokamak with the goal of assessing the potential of alternative divertor geometries and for the validation of theoretical models. L-mode experiments reveal that increasing connection length and hence divertor volume by either increasing poloidal flux expansion or divertor leg...
Linda Sugiyama
(M.I.T.)
23/10/2018, 08:30
Poster
Small applied nonaxisymmetric magnetic fields have been demonstrated to have strong and complex effects on otherwise axisymmetric toroidal fusion plasmas. Their importance raises the question of the best ``steady state'' plasma configuration to use for their analysis. A steady state that is valid on fast time scales of a few Alfvén times is needed to invert and interpret experimental...
Ms
Abha Maheshwari
(ITER-India, Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In-Wall Shield(IWS) Blocks will be inserted between inner and outer shell of ITER Vacuum Vessel. These blocks comprise of number of plates of Stainless Steel stacked together using fasteners of XM-19 and M30 size. Plates are tightened with pretension of 107 kN to withstand EM force of 1.83 × 104N during ITER operation. These bolts are spot welded with blocks to lock any type of rotation. There...
Dr
C Christopher Klepper
(Oak Ridge National Laboratory)
23/10/2018, 08:30
Poster
In preparation for JET Deuterium-Tritium Experiments 2 (DTE-2) and to assure readiness to provide fuel cycle-relevant measurements, the subdivertor fuel isotopic ratio detection limit, as determined by Penning optical gas analysis (OGA) [1, 2], was recently researched. Reevaluation of OGA data from DTE-1 [1] revealed a 1% uncertainty (error bar) at the 1% T/(H+D+T) concentration level. A...
Mr
Gautam Vadolia
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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
Alexey Vertkov
(SC "Red Star")
23/10/2018, 08:30
Poster
The modern results on the implementation of the Russian strategy in the development of designs of long-operating plasma facing element for steady state fusion reactors are considered and analyzed on an example of liquid metal limiters of tokamaks Т-15 and FTU. The experimental validation of this strategy is presented and results on liquid metal CPS behavior in tokamak conditions, effective...
Prof.
Gianmaria De Tommasi
23/10/2018, 08:30
Poster
For a burning plasma device like ITER, radiative power removal by seeded impurities will be inevitable to avoid divertor damage. Increasing divertor radiation by injecting low-Z impurities such as nitrogen, to reduce scrape-off layer heat flux and to cool the divertor plasma to detachment, is put forward as the primary method to achieve this goal. Here, the possibility of increasing the...
Dr
Thomas Schwarz-Selinger
(Max-Planck-Institut für Plasmaphysik)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Among many other favorable properties of tungsten its low intrinsic fuel retention makes it a promising candidate as plasma facing material. However, during operation defects in the tungsten lattice will evolve that will trap hydrogen isotopes. While for present day devices this increased retention is only limited to the near surface it will take place throughout the whole bulk in future...
Dr
Sergey Rogozhkin
(SSC RF ITEP of NRC “Kurchatov Institute”)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The reduced-activation ferritic-martensitic steel Eurofer 97 is the European benchmark structural material for in-vessel components of fusion reactor. Experimental data on neutron irradiated Eurofer 97 material have shown decrease in plasticity and radiation hardening at irradiation temperatures about 300 °C. Formation of dislocation loops and α' pre-precipitates is considered as the main...
Mr
Kiran PATEL
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Bayard-Alpert (BA) type hot cathode ionisation gauge is widely used to measure neutral pressure precisely in vacuum system below 10-3 Torr pressure. Neutral pressure measurement in magnetic confinement fusion experiments is quite challenging for standard BA type gauge due to higher pressure limitation and its ionisation is affected by high magnetic and electrical fields. To overcome above...
Mrs
Valentina Huber
(Forschungszentrum Jülich GmbH)
23/10/2018, 08:30
Poster
The JET ITER-like wall (JET-ILW) combines plasma-facing components (PFC) made of bulk beryllium for main chamber limiter tiles and of bulk tungsten as well as tungsten coated CFC tiles for divertor tiles. The risk of damaging the metallic PFCs caused by beryllium melting or cracking of tungsten owing to thermal fatigue required a new reliable active protection system. To address this issue, a...
Prof.
Sanjeev Varshney
(ITER-India, IPR)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the ITER, an important aspect of qualifying the components to the mandatory regulatory requirements, the system developers have a challenge to first design the components fulfilling guidelines of the ITER recommended French nuclear code RCC-MR (2007) and later on demonstrate to the regulator. It is even more involving for systems that are extending primary vacuum to the interspace and...
Mr
Deepak Sharma
(Institute For Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
India is developing Lead-Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) for testing in ITER for the validation of fusion blanket design tools, tritium breeding performance and high grade heat extraction capability relevant to Indian DEMO. The LLCBTBM will be tested from the first phase of ITER operation (H–H phase) in one half of the ITER port no-2. LLCB TBM set consists of...
Dr
Riscob Bright
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Among the various lithium ceramics, Li2TiO3 is one which has been received much attention due to its very excellent properties, such as reasonable lithium atom density, low activation, excellent tritium release performance and chemical stability, etc. Lithium Titanate [Li2TiO3] pebbles with the diameter of 1mm was widely used for the experiments after successful completion of variety of...
Prof.
Ivan Kodeli
(Jozef Stefan Institute)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the future fusion reactors, such as ITER or DEMO, tritium will be produced by bombardment of lithium atoms with neutrons and several types of special Tritium Breeder Modules (TBM) will be installed in the ITER reactor to demonstrate the self-sufficiency of tritium production. LiF pellets commercially produced as Thermo-luminescent detectors (LiF - TLDs) can be used to measure tritium...
Dr
Teresa Estrada
(CIEMAT)
23/10/2018, 08:30
Poster
Dedicated experiments have been carried out for a systematic comparison of turbulence and radial electric field measured at poloidally separated positions in the same flux-surface in the stellarator TJ-II. The rationale behind this study is twofold, verification of the spatial localization of instabilities predicted by the Gyrokinetic simulations in stellarators and verification of the...
Dr
Edilberto Sánchez
(Laboratorio Nacional de Fusión, CIEMAT)
23/10/2018, 08:30
Poster
In this contribution, recent simulations carried out in stellarator configurations with the global gyrokinetic code EUTERPE and the ongoing validation effort are presented.
The linear relaxation of zonal flows (ZFs) has been studied in global simulations in many stellarator configurations. The code has been verified by comparing results with both other gyrokinetic codes and analytical...
Dr
Susana Clement Lorenzo
(Fusion for Energy)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ITER Remote Experimentation Centre (REC, [1]) in Rokkasho is one of the projects implemented within the Broader Approach (BA) agreement [2] as part International Fusion Energy Research Centre (IFERC). The long-term objective of the REC is to allow researchers to take part in the experimentation on ITER from a remote location. On a shorter time scale, before ITER will be operated, the REC...
Mr
Pramit Dutta
(Institute for Plasma Research)
23/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
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...
