Dr
Marcin Jakubowski
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
10/26/18, 2:00 PM
Poster
Many present and future large magnetic fusion experiments need to consider the 3D topology of the heat and particle exhaust either due to application of external magnetic perturbations to mitigate type-I ELMs or because it is typically inherent to the magnetic configuration of the device (e.g. LHD or W7-X). In both cases, the scrape-off layer forms heterogeneous 3D structures of field lines...
Mr
Riccardo Ragona
(Laboratory for Plasma Physics, LPP-ERM/KMS)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Travelling Wave Array (TWA) antennas distributed all along the periphery of the tokamak are presently considered as Ion Cyclotron Resonance Frequencies (ICRF) heating solution for the DEMO reactor. Compared to the conventional ICRF antenna systems currently in use or designed for future machines like ITER, the TWA consists of antenna sections integrated in the breeding blanket all around the...
Mr
ZUBIN SHAIKH
(DEPARTMENT OF PHYSICS, SAURAHTRA UNIVERSITY, RAJKOT, INDIA)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The confinement by multi-cusp magnetic field configuration is being revisited in prospect of developing a Negative Ion Beam source for heating the plasma in fusion devices. For this, an experimental device namely the Multi-cusp Plasma Device (MPD), has been constructed to study the physics of plasma confinement in a multi-cusp configuration. In this experiment alkali ions of low ionization...
Dr
Roberto Cavazzana
(Consorzio RFX)
10/26/18, 2:00 PM
Poster
The RFX toroidal device (R – major radius=2.0 m, a - plasma minor radius=0.457 m, b - shell minor radius=0.535 m; in operation 1992-1999) was designed to be operated in Reversed Field Pinch (RFP) configuration with a plasma current up to 2 MA. RFX-mod (R=2.0 m, a=0.459 m, b=0.512 m; in operation 2004-2015) was then equipped with 192 independently driven full coverage saddle coils to achieve...
Prof.
Bernhard Unterberg
(Forschungszentrum Jülich)
10/26/18, 2:00 PM
Poster
Tungsten is envisaged as plasma-facing material in fusion reactors because of its small tritium retention and low erosion rate as well as its high melting point and high thermal conductivity. However, its intrinsic and operation-induced brittleness and the unacceptably high oxidation rate at high temperatures pose challenges for manufacturing, component lifetime and safety. The development of...
Mr
amitkumar patel
(institute for plasma research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The positive or negative ion sources which form the primary component of neutral beam injection (NBI) in controlled nuclear fusion using magnetic confinement have to meet simultaneously several demanding requirement like to produce high current, high energy and low-emmitance stable H- ion sources and to confine them etc [1]. It is very well known that multi cusp magnetic fields can confine...
Dr
Carsten Killer
(Max-Planck-Institute for Plasma Physics, Greifswald, Germany)
10/26/18, 2:00 PM
Poster
Wendelstein 7-X (W7-X) recently concluded its first operation phase (OP1.2a) featuring an island divertor. In this concept, the heat and particle exhaust to the divertors is governed by intrinsic three-dimensional magnetic islands at the plasma edge. In order to establish high performance plasmas with safe divertor operation, a comprehensive understanding of the island divertor physics is...
Mr
Baurzhan Chektybayev
(Institute of Atomic Energy of National Nuclear Center of Republic Kazakhstan)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the paper is described concept of non-contact temperature measuring technique of metallic surface is currently being developed for KTM tokamak. Suggested technique is based on using thermographic camera and infrared carbon dioxide laser (CO2) with 10.6 micrometer wavelength. The pulsed IR laser radiation is used to observe changes in the emissivity of the body. This information will give...
Mr
Jaewook Kim
(KAIST)
10/26/18, 2:00 PM
Poster
We perform a correlation analysis to explore how the magnetic Kubo number evolves during and after an abrupt edge pedestal collapse generating stochastic magnetic fields in the simulation. During abrupt edge pedestal collapse caused by type-I ELM (Edge Localized Mode), the stochastic magnetic field is thought to be a possible way to induce significant cross-field diffusion. We analyze the...
Mr
Kartik Mohan
(ITER-India,IPR)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER require 20 MW of RF power to a large variety of plasmas in the Ion Cyclotron frequency range for heating and driving plasma current. Eight RF sources of 2.5MW RF power level each collectively will accomplish the above requirement. Each RF source consists of Solid State Power Amplifier (SSPA), driver, and end-stage, above which driver and end-stage amplifier are a tube (Tetrode/Diacrode)...
Dr
Jitendra Kumar
(Institute for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
SYstem for Microwave PLasma Experiments (SYMPLE) is an experimental system set up at the Institute for Plasma Research (IPR), Gandhinagar, India, to investigate the physics of linear and nonlinear interaction of high-power microwave (HPM) with plasma. BWO based HPM source, proposed to be used for these studies, generates pulsed (~50 ns) microwave power of ~500MW at 3GHz frequency in TM01...
Mr
TARUN KUMAR SHARMA
(ITER-India, Institute for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ITER Cryostat, the largest stainless steel vacuum pressure chamber ever built which provides the vacuum confinement to components operating in ITER ranging from 4.5 k to 80 k. Cryostat Design Model was qualified[1] by ITER. As a Safety Important Class system, Design qualification at every change in its development and installation phases is mandatory. The Cryostat system is currently at...
Mr
Rajiv Sharma
(Institute for Plasma Research (An Autonomous Institute under Department of Atomic Energy,Govt. of India))
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Electrical insulation breaks are very critical component of large-scale fusion devices employing superconducting magnets. The electrical insulation breaks developed for the requirement of up gradation of hydraulics for the superconducting polodial field coils (SC) of SST-1 fusion machine. The electrical insulation breaks have been installed in the hydraulic, validated and sustained the...
Mr
MANOJKUMAR PATEL
(PATEL)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER-India is developing Ion Cyclotron Heating & Current Drive (ICH&CD) RF source in the frequency of 35 to 65 MHz. Three cascaded amplifiers along with low power RF section, AC/DC power supplies and controls will be used for getting MW level RF power from one source. In the present configuration, two tube based tuned amplifiers, i.e. driver (150 kW) and final (1.7 MW) stage amplifiers are...
Dr
BANDYOPADHYAY MAINAK
(ITER-INDIA, INSTITUTE FOR PLASMA RESEARCH)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The characteristics of a negative hydrogen ion (H-) source and its neutralization mainly determine the performance of a negative ion based neutral beam injector (NNBI) performance. Ion source possesses many technological challenges in terms of production of uniform, extracted and accelerated negative ion beam current and also its transport to the tokamak plasma or the beam dump without...
Mr
AKHIL JHA
(ITER-INDIA, INSTITUTE FOR PLASMA RESEARCH)
10/26/18, 2:00 PM
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 HPP3 are RF tube based...
Dr
Ahmet Y. Aydemir
(National Fusion Research Institute, Daejeon, Korea)
10/26/18, 2:00 PM
Poster
In the simplest, magnetohydrodynamic (MHD) description of the plasma equilibrium, rapid transport along the field lines leads to a state where the plasma density and temperature are constant on flux surfaces, exhibiting symmetry in both the poloidal and toroidal directions.
This idealization, however, breaks down at the plasma edge where both the magnetic topology and various perpendicular...
Dr
Eleonora Viezzer
(University of Seville)
10/26/18, 2:00 PM
Poster
Heat and momentum transport play a key role in achieving high confinement in fusion plasmas. Recent advances in the diagnostic capabilities at AUG now allow us to measure the edge profiles on a sub-ms to ms time-scale and with a spatial resolution of less than 5 mm, making it ideal to study the profile recovery after an ELM crash. Here, we present the dynamic behaviour of the energy and...
Dr
Athina Kappatou
(Max-Planck-Institut für Plasmaphysik, Garching, Germany)
10/26/18, 2:00 PM
Poster
The presence of fusion-produced helium is fundamentally connected to the performance of a fusion reactor. Not only will He ash dilute the fusion fuel if not removed promptly, but the presence of He in a D plasma is reported to negatively affect the plasma confinement [1]. Furthermore, He plasmas are a choice for the ITER non-nuclear phase, but the energy confinement in such plasmas is...
Chang Liu
(Princeton Plasma Physics Laboratory)
10/26/18, 2:00 PM
Poster
The effects of kinetic instabilities on the dynamics of runaway electrons in momentum space is investigated using a newly-developed simulation model, and the anomalous dissipation and the fast pitch angle scattering of runaway electrons in low energy are explained. The interaction of runaway electron avalanche and the kinetic instabilities are studied self-consistently using quasilinear model....
Mrs
Manika Sharma
(Institute for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The evolution of data acquisition system (DAS) for steady-state operation of Tokamak has been technology driven. Steady-state Tokamak demands a data acquisition system which is capable enough to acquire data losslessly from diagnostics. The needs of loss less continuous acquisition have a significant effect on data storage and takes up a greater portion of any data acquisition Systems. With...
Mr
Michael Houry
(CEA)
10/26/18, 2:00 PM
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Dr
Annika Ekedahl
10/26/18, 2:00 PM
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Dr
Lionello Marrelli
(Consorzio RFX)
10/26/18, 2:00 PM
Poster
In this contribution the main achievements of the RFX-mod Reversed Field Pinch (RFP) are summarized as the basis for a substantial upgrade of the device. The RFX-mod active MHD control system successfully controlled MHD instabilities such as Resistive Wall Modes and mitigated localized Plasma Wall Interaction by avoiding Tearing Modes wall-locking. This allowed producing the highest RFP plasma...
Inessa Bolshakova
(Lviv Polytechnic National University)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Dr
Jugal Chowdhury
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543-451, USA)
10/26/18, 2:00 PM
Poster
The X-point height relative to the divertor plates may cause difference in the neutral particle penetration into pedestal and have impact on the pedestal physics in H-mode. In the present work, we utilize the total-f global gyrokinetic neoclassical code XGCa to study the X-point height effect on the ExB flow profile in a JET-like H-mode pedestal in a realistic JET-like divertor geometry and...
Dr
Francois Ryter
(Max-Planck-Institut fuer Plasmaphysik)
10/26/18, 2:00 PM
Poster
Turbulence-driven ion heat transport in tokamak H-modes is driven by
the ion temperature gradient (ITG) instability,
while electron heat transport is driven by the ITG, trapped electron
mode (TEM) and/or electron temperature gradient (ETG) instabilities.
These three instabilities appear above their respective threshold in
normalized temperature gradient
(R/LT) and drive transport.
We...
Mr
Sergey Bozhenkov
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
10/26/18, 2:00 PM
Poster
In this contribution we present details of recent W7-X pellet injection experiments and discuss properties of the achieved plasmas. Hydrogen pellet injections allowed to raise the electron density above $1.2 \cdot 10^{20}$ m$^{−3}$ and to establish: (i) operation above the cut-off for the X2 polarization of the 140 GHz electron cyclotron resonance heating (ECRH); (ii) stable divertor heat flux...
Mr
Raymond O'Neill
(General Atomics)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
R.C. O’Neill1, M. Brookman1, J.S. deGrassie1, B. Fishler1, M. LeSher1, C. Moeller1, C. Murphy1, A. Nagy2, M. Smiley1, J. F. Tooker1, H. Torreblanca1
1General Atomics, PO Box 85608, San Diego, California 92186-5608, USA
2 Princeton Plasma Physics Laboratory, Princeton NJ 08543, USA
Corresponding author: oneill@fusion.gat.com
A new current drive system is being designed and...
Dr
Klaus Hallatschek
(Max-Planck-Institute for Plasma Physics)
10/26/18, 2:00 PM
Poster
Gyrokinetic and non-local fluid codes have complementary limitations in the tokamak
edge. To arrive at a common basis, the gyrokinetic code CGYRO and the non-local
two-fluid code NLET have both been applied to identical parameters sets ranging from
resistive ballooning turbulence - approaching the collisional fluid limit - relevant
to the edge of a tokamak, up to high-gradient kinetic ITG...
331.
Impact of an edge resonant transport layer on fast-ion confinement in the ASDEX Upgrade tokamak
Mr
Joaquin Galdon-Quiroga
(University of Seville)
10/26/18, 2:00 PM
Poster
An edge resonant transport layer has been found to explain many aspects of fast ion confinement under symmetry breaking 3D edge perturbations, such as edge localized modes (ELMs) and externally applied magnetic perturbations (MPs).
Experimental measurements in the ASDEX Upgrade (AUG) tokamak show that fast ion losses in the presence of symmetry breaking 3D fields strongly depend on the...
Dr
Mike Dunne
(IPP-Garching)
10/26/18, 2:00 PM
Poster
Pedestal data from ASDEX Upgrade (AUG) and Alcator C-Mod are presented. Scans of impurity content have been performed in both machines, reaching states where the outer divertor is partially or fully detached. The impact of impurity seeding on pedestal structure is compared. In the analysed scenarios, nitrogen seeding increases the achievable pedestal top pressure in AUG, while excessive...
Dr
Matthias Willensdorfer
(IPP Garching)
10/26/18, 2:00 PM
Poster
One method to mitigate or even suppress the repetitive impulsive energy loss due to edge localised modes (ELMs) is the application of externally applied non-axisymmetric magnetic perturbation (MP)-fields.
In high confinement mode (H-mode) plasma, these externally applied MP-fields excite marginally stable ideal kink modes at the edge, which amplify the MPs. These kink modes cause a...
Mr
Chandra Kishor Gupta
(Institute For Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
This paper conceptualizes shunt active power filter (SAPF) using synchronous-reference- frame (SRF) theory to mitigate the harmonics present in the power system. The shunt active power filter injects a suitable compensating current at a point called point of common coupling (PCC) so that the harmonics present in the line are cancelled out and sinusoidal nature of current waveforms is restored....
Mr
Rakeshkumar Patel
(Institue for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The static heat loads on the 80 K thermal shields of SST-1 will be removed using single phase liquid nitrogen cooling at 0.7 MPa. The single phase liquid nitrogen is obtained using 80 K liquid nitrogen booster system. Booster system is in form of three storey building as pump cryostat at bottom, sub-cooler vessel cryostat at middle and pressurized vessel cryostat at upper. Boosting system...
Diego del-Castillo-Negrete
(Fusion Energy Division. Oak Ridge National Laboratory)
10/26/18, 2:00 PM
Poster
The dynamics of runaway electrons (RE) is a complex process and, although significant progress has been made in the understanding of individual isolated pieces of the puzzle, a predictive capability calls for an Integrated Simulation (IS) effort. In this presentation we report on recent progress on this problem. The goal is to use the BMC method [1] to couple a kinetic description of the RE...
Dr
Donald Spong
(Oak Ridge National Laboratory)
10/26/18, 2:00 PM
Poster
Runaway electrons are of significant interest in tokamaks due to their potential for damage to plasma facing components. Runaways are of particular concern following disruptions when the plasma undergoes a thermal quench and a subsequent current quench; these lead to large loop voltages that can rapidly create runaways. Due to the risks of performing intense runaway experiments, the generation...
Dr
Novimir Pablant
10/26/18, 2:00 PM
EXC - Magnetic Confinement Experiments: Confinement
Post Deadline
Prof.
Jean-Marie Noterdaeme
(Max Planck Institute for Plasma Physics)
10/26/18, 2:00 PM
Poster
Significant progress in applying ICRF power to ASDEX Upgrade (AUG) has been achieved in the last years; this progress has been associated with a similar progress in our understanding and capability to model the relevant processes. The two main challenges of the ICRF system (power coupling and impurity production) have been tackled successfully.
First, the outer mid-plane gas injection...
Dr
Carlos Silva
(IST/IPFN)
10/26/18, 2:00 PM
Poster
Information of the plasma density is essential for the study and operation of magnetically confined fusion devices. Microwave reflectometry appears as an attractive diagnostics due to its high temporal and spatial resolution and its application to profile as well as fluctuation measurements.
The microwave reflectometry systems developed by IST for ASDEX Upgrade consist of: (i) multi-band...
Dr
Eric Nardon
10/26/18, 2:00 PM
PPC - Plasma Overall Performance and Control
Poster
Mr
Hiteshkumar Kantilal Patel
(ITER India, Institute for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
High heat flux components form the primary interface of thermal management of injectors in the fusion devices. The requirement for such application varies from 1 to 10MW/m2. UHV compatibility is the inherent characteristics of such components also manufacturing processes involves the development of specific material, process qualification of special process like EB welding and component...
Dr
Jeremy Lore
(ORNL)
10/26/18, 2:00 PM
Poster
Experiments were performed in short pulse operation (OP1.2) on the Wendelstein 7-X (W7-X) stellarator using a set of five magnetic configurations that were designed to mimic the topology and resultant divertor fluxes of a high-power long-pulse scenario that is predicted to cause component overload. These experiments demonstrated the capability of edge transport simulations to accurately...
Mr
Jayant Patel
(Institute for Plasam Research, Bhat Indira Bridge, Gandhinagar, Gujarat, India)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Institute for Plasma Research has 1.3 kW helium refrigerator/liquefier (HRL) cryogenics system, which is in operational state since 2003. The cryogenic HRL plant used to cool down the magnets of Steady State Super-conducting Tokomak (SST-1). Three identical Mycom make helium screw compressors with Fimet make 315 kW Electrical Motor, Oil removal system operate to supply high-pressure helium...
Dr
Yves Peysson
(CEA)
10/26/18, 2:00 PM
Poster
The sudden termination of a plasma discharge known as a major disruption is a well-identified difficulty from the beginning of tokamak research, which remains still today particularly problematic for the design of a reliable fusion reactor. The key questions are principally related to the growth rate of relativistic electron population, closely linked to the level of the critical electrical...
Dr
Raghvendra Singh
(National Fusion Research Institute)
10/26/18, 2:00 PM
Poster
Raghvendra Singh1, Hogun Jhang1 and Maolin Mou2, 3
1National Fusion Research Institute, Daejeon 305-333, Republic of Korea
2College of physical Science and Technology, Sichuan University, 610065 Chengdu, China 3Key Laboratory of High Density Physics and Technology of Ministry of Education, Sichuan University, Chengdu, 610064, China
Email address: rsingh129@nfri.re.kr;...
Olivier Agullo
(Aix-Marseille Université)
10/26/18, 2:00 PM
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
Dr
Vinodh Kumar Bandaru
(Max-Planck-Institute for Plasma Physics, Garching)
10/26/18, 2:00 PM
Poster
Uncontrolled termination of post-disruption runaway electron (RE) current can cause deep localized melting of the first wall and this poses a serious challenge to the successful operation of fusion grade tokamaks, including ITER. Since the deconfinement of REs depends on the timescale of flux surface reformation and the plasma stability itself is affected by the runaway current, the...
Dr
Guanqi Dong
(SWIP)
10/26/18, 2:00 PM
Poster
Quiescent H-mode (QH-mode) was first discovered in DIII-D as an ELM-free H-mode regime, which is usually accompanied by the presence of edge harmonic oscillations (EHOs). EHOs are believed to provide necessary transport to eliminate ELMs by dynamics of the plasma itself. The saturated kink-peeling mode has been suggested as a possible candidate for EHO. In this work, we consider another...
Dr
Nathaniel M. Ferraro
(UsPPPL)
10/26/18, 2:00 PM
Poster
Vertical displacement events (VDEs) where the plasma moves rapidly towards the wall can cause large electromagnetic forces on the vessel structures with possible damaging effects for large tokamaks. Non-axisymmetric modes developing during the VDE can lead to asymmetric, sometimes rotating forces on the vessel which can be even more severe. Large-scale 3D simulations play a crucial role on the...
Dr
Yang Li
(Department of Engineering Physics, Tsinghua University, Beijing 100084, China)
10/26/18, 2:00 PM
Poster
Meso-scale size structures including the blobs in the edge plasma can not only transport particle and heat out, but may also contribute to the plasma poloidal/toroidal rotation, namely, the momentum transport.[1] Turbulent parallel momentum stress can be divided into three components, which are diffusive, covective and residual parts. In the presented work, the triplet nonlinear term is...
Dr
Ulrich Fischer
(Karlsruhe Institute of Technology)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The European Roadmap to the realisation of fusion energy considers the stellarator concept as a possible long-term alternative to a tokamak fusion power plant (FPP). A corresponding R&D programme is conducted by the EUROfusion consortium to advance the stellarator concept with the scientific exploitation of the W7-X experiment. The aim is to optimise the stellarator performance, prove the...
Mr
Mahesh Ghate
(Institute For Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Fusion relevant high field superconducting magnets require large current carrying conductor of the order of tens of kilo-Amperes. High current carrying the cable in conduit conductor (CICC) are based on low-temperature NbTi and Nb3Sn superconductors. The manufacturing of superconducting cable is carried out by twisting required strands into the desired configuration by application of tensile...
Mr
JATINKUMAR PATEL
(INSTITUTE FOR PLASMA RESEARCH)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Electron Cyclotron Resonance Heating (ECRH) is one of the essential RF heating system used for pre-ionization and heating experiments in Aditya and SST1 tokamak. The 42 GHz gyrotron system capable of delivering 500kW RF power for 500ms has been installed for operation with Aditya and SST1 tokamak. Gyrotron operation requires a systematic and sequential controlled operation of different...
Piero MARTIN
(Consorzio RFX)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Divertor Tokamak Test Facility (DTT) is a new tokamak whose
construction has recently been approved by the Italian government. DTT
will be a high field superconducting toroidal device (6 T) carrying
plasma current up to 6 MA in pulses with length up to 100s, with an
up-down symmetrical D-shape defined by major radius R=2.10 m, minor
radius a=0.65 m and average triangularity 0.3. The main...
Dr
Olaf Grulke
(MPI for Plasma Physics)
10/26/18, 2:00 PM
Poster
A primary goal of Wendelstein 7-X (W7-X) operation is to demonstrate stationary, long pulse discharges at fusion-relevant plasma densities and temperatures. Studies on the behavior and the control of impurity ions originating from plasma-wall-interaction with the divertor and other plasma facing components is a crucial issue potentially leading to a thermal collapse and dilution of the fuel....
Dr
Andreas Dinklage
(Max-Planck-Institut für Plasmaphysik)
10/26/18, 2:00 PM
Poster
Plasma termination by excess fuelling or impurity interaction is a safety relevant event in potential fusion reactors. Sudden termination of plasma operation is an aspect that enters material requirements in terms of released energies, localization and respective time-scales of the plasma terminating event. In tokamaks, such events may lead to disruptions or thermal quenches. While disruptions...
Dr
Apiwat Wisitsorasak
(King Mongkut's University of Technology Thonburi)
10/26/18, 2:00 PM
Poster
Core-Edge simulations of the low confinement mode (L-mode) plasma are carried out using 1.5D BALDUR integrated predictive modeling code in. In each simulation, the plasma current, temperatures, and density profiles for both core and SOL regions are self-consistently evolved. The plasma profiles in the SOL region are simulated by integrating the fluid equations, including sources, along and...
Dr
Jozef ONGENA
(Plasma Physics Lab, ERM-KMS, Brussels)
10/26/18, 2:00 PM
Poster
An important aim of W7-X is to demonstrate fast ion confinement at volume averaged beta values up to 5% for which W7-X was optimised [1]. These high beta values correspond to plasma densities above 10^{20}m^{-3}. Mimicking the behaviour of alpha particles in a future stellarator requires the presence of energetic ions with energies in the range ~100 keV in the core of W7-X high density plasmas...
Mr
David Rittich
(Max-Planck-Institut für Plasmaphysik)
10/26/18, 2:00 PM
Poster
The neutral beam (NB) driven current, like the other intrinsic and driven current contributions to the total plasma current, is not directly measurable. Therefore, two strategies are used to investigate neutral beam current drive (NBCD). First, for quantitative investigations of the total NB driven current the measured total plasma current is compared with the sum of the calculated...
Dr
pengyuan li
(southwestern institute of physics)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
see attachment
Lorenzo Frassinetti
(KTH, Royal Institute of Technology)
10/26/18, 2:00 PM
Poster
The role of the pedestal pressure position ($p_e^{pos}$) in the pedestal stability has been recently highlighted in deuterium (D) plasmas in AUG [1], where it was shown that an outward shift of the pressure can lead to a reduction in pedestal pressure height ($p^{ped}$). The work emphasized the role of scrape-off layer conditions and possibly separatrix density ($n_e^{sep}$) in the global...
Mr
RAJNISH KUMAR
(Scientific Officer-F)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Ion Cyclotron Heating and Current Drive (ICH&CD) system is one of the important auxiliary heating and current drive systems for ITER experiment [1]. Total 20 MW of IC power is required to couple with ITER plasmas using 8 independent RF sources (35-65MHz) having power handling capability of 2.5 MW at VSWR of 2:1 with other stringent specifications. To finalise the source configuration, an R&D...
Dr
Gergo Pokol
(NTI, Budapest University of Technology and Economics, Hungary)
10/26/18, 2:00 PM
Poster
Relativistic runaway electrons are of major concern in tokamaks. Some nice tools have been developed in the recent decades, but we still miss a self-consistent simulation tool that could simultaneously capture all aspects of this phenomenon. The EUROfusion Code Development for integrated modelling project (WPCD) facilitates integration of different plasma simulation tools this by providing an...
Dr
Valentin Igochine
(Max-Planck-Institut für Plasmaphysik)
10/26/18, 2:00 PM
Poster
Tearing mode formation after internal crash events like sawteeth or fishbones is one of the most important MHD processes that result in a big island structure and associated confinement degradation in tokamaks. This type of tearing mode formation is considered to be the most important for future fusion reactors like ITER, because large internal events provide strong magnetic perturbations and...
Ms
Renu Bahl
(Institute For Plasma Research,)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A 60 MHz Rod type Radio Frequency Quadrupole Accelerator has been designed for material studies through Ion Irradiation at Institute For Plasma Research, Gandhinagar. Ion Irradiation has been preferred for characterization of fusion research material properties due to its inherited advantages of 1) absence of high residual radioactivity 2) well defined energy, dose rate and temperature values...
Dr
Indranil Bandyopadhyay
(ITER-India, Institute for Plasma Research)
10/26/18, 2:00 PM
Poster
Plasma Major Disruptions (MDs), Vertical Displacement Events (VDEs) and associated runaway electron currents in ITER are a major cause of concern in ITER operations. Major R&Ds, both experimental and well as through theory and modeling is underway across the fusion community to understand these events and find suitable amelioration techniques. In the past we have presented detailed predictive...
Dr
Nicola Vianello
(Consorzio RFX, Padova, Italy)
10/26/18, 2:00 PM
Poster
Addressing the role of Scrape Off Layer filamentary transport is a subject of intense studies in fusion science. Intermittent structures dominate transport in L-Mode and strongly contribute to particle and energy losses in H-mode. The role of convective radial losses has become even more important due to its contribution to the shoulder formation in L-Mode, describing the progressive...
Dr
Rudolf Brakel
(Max-Planck-Institut für Plasmaphysik, Greifswald, Germany)
10/26/18, 2:00 PM
Poster
Wall conditioning in fusion devices is prerequisite to provide controlled boundary conditions for operation and to achieve high performance plasmas. Major issues are to achieve low outgassing, low particle recycling and a low impurity level. Implementation and optimisation of a systematic wall conditioning strategy was a major issue during the second operation campaign at the superconducting...
537.
Studies of the gas puff effect on edge plasma of Aditya tokamak using coupled DEGAS2-UEDGE code
Dr
Ritu Dey
(Institute for Plasma Research)
10/26/18, 2:00 PM
Poster
Fuel neutral penetration and dynamics in the edge and scrape of layer (SOL) plasma region of tokamaks shape the plasma properties in these regions which play an important role in determining the core plasma confinement. Experiments in Aditya and Aditya-U tokamaks have shown that fuelling by periodic multiple gas puffs led to improved core plasma properties [1]. These experimental results...
Mr
Kedar S BHOPE
(Institute for Plasma Research , BHAT, Gandhinagar, -382428,Gujarat,INDIA), Mr
Ramesh Kumar B Buddu
(Institute for Plasma Research , BHAT, Gandhinagar, -382428,Gujarat,INDIA)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Fusion reactor components manufacturing is mainly deals with Austenitic stainless steels with different type welding techniques and kind of weld structure joints. Thick steel like 40 mm & 60 mm plates are used mainly in the fabrication of vacuum vessel, divertor and other supporting structures with different weld joining techniques like Tungsten Inert Gas (TIG) welding, Narrow Groove TIG...
Prof.
Ambrogio Fasoli
(EPFL Swiss Plasma Center)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The range and the reactor relevance of the TCV experiments are being enhanced by two sets of major upgrades. The first set includes the installation of neutral beam injection (NBI) and new Electron Cyclotron (EC) power sources, to heat the ions and vary the electron to ion temperature ratio, in plasmas with ITER relevant β values. A 15-30keV, 1MW, 2s tangential NBI system is operational on TCV...
Dr
Braj Kishore Shukla
(Institute for Plasma Research)
10/26/18, 2:00 PM
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Gyrotron based electron Cyclotron resonance Heating (ECRH) system is used on tokamaks Aditya-U and SST-1. The ECRH system consists of High power Gyrotron, corrugated waveguide based transmission line and a quasi-optical launcher.
The 42GHz Gyrotron delivers 500kW power for 500ms duration. This Gyrotron operates at ~ - 48kV beam voltage and +18kV anode voltage. This system draws around 20A...
Dr
Shaocheng Liu
(Institute of Plasma Physics Chinese Academy of Sciences)
10/26/18, 2:00 PM
Poster
Wendelstein 7-X (W7-X) was operated successfully with the first divertor plasma in the operation phase 1.2a (OP1.2a). A new combined probe head, which consists of Langmuir probe pins, Mach probe, ion sensitive probe (ISP), differential coil and a tri-axial pick-up coil, is able to measure the edge plasma profiles (T$_e$,n$_e$,ϕ$_f$,M$_∥$), magnetic field, poloidal and radial turbulence...
Dr
Thomas Pütterich
(Max-Planck-Institut für Plasmaphysik)
10/26/18, 2:00 PM
Poster
At ASDEX Upgrade experiments have been performed, in which important features of the ITER baseline (ITER BL) scenario are matched or imitated. A crucial property of the ITER BL scenario is the combination of $q_{95}=3$ with strong plasma shaping, which leads to ELM frequencies ($f_{ELM}$) as low as 10Hz, while the ELMs are very large.
One consequence of the low $f_{ELM}$ is that access to...
Richard Majeski
(Princeton Plasma Physics Lab)
10/26/18, 2:00 PM
Poster
The research program for LTX-beta, the upgrade to the Lithium Tokamak Experiment, combines lithium walls to produce gradient-free temperature profiles and stabilize ion and electron temperature gradient-driven modes, with approaches to stabilization of density gradient-driven modes, such as the trapped electron mode (TEM). Candidate stabilization mechanisms for the TEM include sheared flow...
Dr
R.W. (Bob) Harvey
(UsCompX)
10/26/18, 2:00 PM
Poster
The runaway electron distributions driven by a large toroidal electric field Etor induced by the drop in the temperature profile due to disruption or pellets are comprehensively simulated by the 3D Fokker-Planck solver CQL3D [1], recently coupled to the Ampere-Faraday (A-F) equations. The evolution of the toroidal current in a plasma occurs on a resistive time scale tr, which is typically of...
