Dr
Paulo Rodrigues
(Instituto de Plasmas e Fusao Nuclear)
10/15/14, 8:30 AM
Poster
A systematic approach to assess the linear stability of Alfvén eigenmodes in the presence of fusion-born alpha particles is described. Because experimental results for ITER are not available yet, there is no guidance about which Alfvén eigenmodes will interact more intensively with the fast-particle population. Therefore, the number of modes that need to be considered in stability assessments...
Dr
Marco Wischmeier
(Max-Planck-Insitut für Plasmaphysik)
10/15/14, 8:30 AM
Poster
Power exhaust is a crucial issue for future fusion devices such as ITER and DEMO. A device like DEMO despite being of a similar geometrical size of ITER will need to accommodate an about 3 to 4 times higher thermal power, aggravating the issue of power exhaust. ASDEX Upgrade with its fully tungsten covered wall, high ratio of heating power to major radius and extensive edge and SOL diagnostics...
Dr
Maxim Isaev
(Kurchatov Institute)
10/15/14, 8:30 AM
Poster
Alfvén eigenmode instability analysis in ITER steady-state plasma scenarios with reversed magnetic shear was performed with the NOVA and TAEFL codes [1]. In our work for this scenario we explore the stability of Alfvén eigenmodes with the KINX code [2]. Both isotropic fusion alphas and beam ions contribute into the mode drive. Fast particle dynamics, linear growth rate, mode amplitude...
Dr
Alexei R. POLEVOI
(ITER Organization)
10/15/14, 8:30 AM
Poster
Operational space (I_p-n) for long pulse scenarios (t_burn ~ 1000 s, Q > 5) foreseen in ITER was assessed by 1.5D core transport modelling with pedestal parameters predicted by the EPED1 code. The analyses include the majority of transport models (CDBM, GLF23, Bohm/GyroBohm (BgB), MMM7.1, MMM95, Weiland, Scaling-Based) presently used for interpretation of experiments and ITER predictions. The...
Mr
Yury Gott
(Kurchatov Institute)
10/15/14, 8:30 AM
Poster
The possibilities of using transverse ICRF heating tokamak plasma minorities for toroidal current driving is investigated in this paper.
Three ways of this heating utilization are proposed. Firstly, such heating gives possibility to drive the seed current near magnetic axis, secondly, it can be used for safety current profile adjusting (the negative shear producing) due to synchronous heating...
Prof.
Sadao Masamune
(Kyoto Institute of Technology)
10/15/14, 8:30 AM
Poster
Improvement of plasma performance has been advanced in the low-aspect-ratio (low-A) reversed field pinch (RFP) RELAX, whose main objectives include exploring the low-A RFP configuration. In axisymmetric RFP states in deep-reversal region, it is found that central electron poloidal beta, beta_p (=p_e0/(B_pa^2/(2mu_0))), which almost equals the electron beta in the RFP, has reached to 5~10%....
Dr
Ivo Furno
(EPFL- CRPP)
10/15/14, 8:30 AM
Poster
TORPEX is a flexible device dedicated to investigating basic plasma physics phenomena of importance for fusion. It can feature a simple magnetized toroidal (SMT) configuration with a dominant toroidal magnetic field and a small vertical field component, or accommodate closed field-line configurations using a current-carrying conductor suspended in the center of the chamber. This produces a...
Mr
Todd E. Evans
(USA)
10/15/14, 8:30 AM
Poster
Joint experiments on the DIII-D tokamak and the LHD stellarator/heliotron have resulted in the discovered of spontaneous heat transport bifurcations across the O-point of an applied m/n=2/1 magnetic islands in DIII-D and enhanced particle transport relative to heat transport in edge m/n=1/1 LHD isalnds. The DIII-D results suggest that the heat transport bifurcations are due to islands...
Dr
Bo Lyu
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/15/14, 8:30 AM
Poster
Access to high-confinement plasmas on the EAST tokamak was readily achieved through LHCD, ICRF, or their combined application along with improved wall conditioning and wave-plasma coupling capabilities. Using a tangentially viewing X-ray crystal spectrometer, core plasma rotation profiles and their temporal evolutions were obtained. This paper presented typical plasma rotation behaviors for...
Dr
Frédéric Imbeaux
(CEA-IRFM)
10/15/14, 8:30 AM
Poster
The ITER Integrated Modelling & Analysis Suite (IMAS) will support both plasma operation and research activities on the ITER tokamak experiment. The IMAS will be accessible to all ITER Members as a key tool for the scientific exploitation of ITER. It will allow collective development of Integrated Modelling tools, by sharing data, code components and, ultimately, workflows based on coupling...
Dr
Giuseppe Calabro
(ENEA - Italy)
10/15/14, 8:30 AM
Poster
Snow Flake Divertor (SFD) configuration has been proposed as one valid way to reduce the plasma-wall interaction. For technological reasons, SFD configuration is difficult to realize and control in real experiments, especially for a tokamak like EAST that does not have dedicated divertor coils designed to locally shape the magnetic field topology. For this reason, Quasi-SFD (QSF) static...
Mr
Pavel Minashin
(NRC "Kurchatov Institute")
10/15/14, 8:30 AM
Poster
A model is suggested for calculating the efficiency of multi-pass absorption of EC heating wave in tokamaks at initial stage of discharge, and the effect on the start-up in ITER-like tokamak is analyzed. The single-pass absorption of injected EC wave is evaluated with the scaling obtained using the OGRAY code. The model for subsequent multi-pass absorption, after first reflection of the EC...
Mr
Andrew Kirk
(UK)
10/15/14, 8:30 AM
Poster
The application of Resonant Magnetic Perturbations (RMPs) is foreseen as a mechanism to ameliorate the effects of ELMs on the ITER divertor. Various aspects of RMP operation crucial to ITER have been demonstrated on MAST such as mitigating the first ELM after the L-H transition, sustaining ELM mitigation during both the current ramp-up and in the event of failure of a sub-set of the in-vessel...
Prof.
Yunfeng Liang
(Forschungszentrum Juelich GmbH)
10/15/14, 8:30 AM
Poster
ELM mitigation has been observed on the Experimental Advanced Superconducting Tokamak (EAST) when lower hybrid waves (LHWs) are applied to H-mode plasmas sustained mainly with ion cyclotron resonant heating (ICRH). This has been demonstrated to be due to the formation of helical current filaments (HCFs) flowing along field lines in the scrape-off layer induced by LHWs. Because of the geometric...
Dr
Michele Romanelli
(CCFE)
10/15/14, 8:30 AM
Poster
ITER operation requires effective fuelling of the core-plasma for conditions in which neutral dynamics through the scrape-off layer is expected to affect significantly the efficiency of gas penetration. In order to assess fuelling requirements in transients as well as in stationary phases, integrated core-edge plasma modelling has been carried out for plasma conditions expected in the...
Dr
Florian Koechl
(Austria)
10/15/14, 8:30 AM
Poster
ITER will reach the burning regime Pfusion/Pinput of ~10 by operating in an ELMy H-mode. Control of the flattop burn phase is a critical demonstration for ITER, showing the simultaneous regulation of the plasma core fuel density, fusion power gain, and consistent divertor operation, under several constraints and perturbations. The ITPA-IOS group is doing time dependent integrated simulations...
Mr
David DOUAI
(CEA, IRFM, Association Euratom-CEA, 13108 St Paul lez Durance, France)
10/15/14, 8:30 AM
Poster
Wall conditioning will be required in ITER to control fuel - and impurity recycling and to improve plasma performance and reproducibility. In the nuclear phase, wall conditioning will also contribute to the control of the tritium (T) inventory within the fuelling cycle. This paper reviews experimental and modelling research activities on wall conditioning in preparation of ITER operation....
Dr
Ken McClements
(CCFE)
10/15/14, 8:30 AM
Poster
Fast particle-driven waves in the ion cyclotron frequency range (ion cyclotron emission or ICE) have provided a valuable diagnostic of confined and escaping fast ions in many tokamaks. This is a passive, non-invasive diagnostic that would be compatible with the high radiation environment of DT plasmas in ITER, and could provide important information on fusion alpha-particles and beam ions in...
Dr
Jose Ramon Martin-Solis
(Universidad Carlos III de Madrid)
10/15/14, 8:30 AM
Poster
Large runaway electron (RE) currents could be formed during the current quench (CQ) phase of ITER disruptions. Although the main interest of studying REs is related to their final deposition on the plasma facing components (PFCs), much less attention has been paid to their termination phase, when the current and the REs are lost. During this phase, conversion of magnetic energy of the runaway...
Dr
Antoine Merle
(Ecole Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas (CRPP), CH-1015 Lausanne, Switzerland)
10/15/14, 8:30 AM
Poster
Dedicated experiments have been performed on the TCV tokamak to compare the inverse scalelengths of the main plasma region with the one observed in the edge region in standard L-mode plasmas. The main plasma region is known to be characterized by a central region with relatively flat profiles, influenced by the sawtooth activity, and a stiff region where the inverse scalelength is relatively...
Dr
Eric M. Bass
(University of California San Diego)
10/15/14, 8:30 AM
Poster
A simple 1D radial transport code predicting the fusion alpha density profiles in an ITER burning plasma unstable to Alfvén eigenmodes (AEs) is illustrated. With the local AE thresholds exceeded only in the mid-core in the baseline case, we find only moderate mid-core flattening of the alpha density (and heating) profile and negligible alpha heating loss. Neglecting “ripple loss,” only...
Dr
Natalia Kirneva
(NRC "Kurchatov Institute")
10/15/14, 8:30 AM
Poster
Studies of high density plasmas approaching the Greenwald limit are timely and necessary in view of future reactor operation, both to gain a phenomenological understanding of their behavior and to validate and improve the theoretical treatment of their stability, confinement and control, as well as the physics underlying the density limit process itself. One of the key features of the TCV...
Dr
Xinjun Zhang
(Institute of Plasma Physics Chinese Academy of Sciences (ASIPP))
10/15/14, 8:30 AM
Poster
The ICRF system of 12.0 MW has been developed for EAST. To support the long pulse operation over 1000s, the ICRF heating system is upgraded with active cooling, especially for ICRF antenna systems. The ICRF system of 6.0MW has been operating in the 2012 experimental campaign. A new 6.0 MW system has been successfully commissioned at full power on water dummy load. In the upcoming campaign，the...
Dr
Gerrit Hogeweij
(FOM)
10/15/14, 8:30 AM
Poster
AUG and JET, the largest present devices with high-Z PFC components, have identified requirements for stable H-mode operation, i.e. to keep heavy impurity concentrations sufficiently low, to avoid central accumulation, radiative collapses and disruptions. Limitations in the operational space which can be accessed in H-mode have been identified, e.g. (i) the need of operating at sufficiently...
Dr
Masaki Nishiura
(The University of Tokyo)
10/15/14, 8:30 AM
ICC - Innovative Confinement Concepts
Poster
This study reports the recent progress in improved plasma parameters of the RT-1 device. Increased input power and the optimized polarization of electron cyclotron resonance heating (ECRH) with an 8.2 GHz klystron produced a significant increase in electron beta, which is evaluated by an equilibrium analysis of Grad-Shafranov equation. The peak value of the local electron beta e was found to...
Dr
Ralph Dux
(Max-Planck-Institut für Plasmaphysik, Garching, Germany)
10/15/14, 8:30 AM
Poster
The effect of a tungsten divertor on the performance of H-mode plasmas in ITER has been investigated by combining scrape-off layer transport calculations performed with SOLPS with core transport simulations using the ASTRA code, which was coupled to the impurity transport code STRAHL. The penetration of W into the central plasma mainly depends on two mechanisms: prompt re-deposition of W to...
Dr
Marcin Jakubowski
(Max-Planck-Institut für Plasmaphysik)
10/15/14, 8:30 AM
Poster
Control of Type-I Edge Localized Modes (ELMs) is an important task for next step fusion devices like ITER. Following the results obtained on DIII-D resonant magnetic perturbations (RMPs) became a very popular tool to control plasma exhaust in tokamaks like ASDEX-Upgrade, MAST, KSTAR and probably ITER. RMPs produce a stochastic boundary which reduces the pressure gradients in the pedestal...
Dr
Roman Zagorski
(Institute of Plasma Physics and Laser Microfusion)
10/15/14, 8:30 AM
Poster
Different plasma performance (energy confinement, discharge duration) has been generally observed in operationally close JET discharges with carbon (C) and ITER-like wall (ILW). Presence of tungsten (W) in ILW discharges is one of the major changes introduced with the wall replacement which may partly explain the differences observed at JET and have an impact on ITER operation. Effect of W on...
Mr
Sergey Konovalov
(NRC "Kurchatov Institute")
10/15/14, 8:30 AM
Poster
Feasibility of the ITER disruption mitigation system (DMS) to a)mitigate heat loads on the divertor target plates and plasma facing components during the thermal quench (TQ) phase of the disruption; b) reduce electromagnetic forces on the vacuum vessel during current quench; c) avoid or control the runaway electron (RE) generation are studied in the present report. Complex variety of physical...
Ms
Lingyan Xiang
(Institute of Plasma Physics, Chinese Academy of Science)
10/15/14, 8:30 AM
Poster
Introducing external impurities into plasma provides an effective means to reduce divertor power load for present and future fusion devices [1]. Dedicated argon (Ar) seeding experiments focusing on the effects of the plasma configuration and seeding position have been carried out in EAST, with the corresponding simulations using SOLPS 5.0 code package being also ongoing.
The double null (DN)...
Dr
Bojiang Ding
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/15/14, 8:30 AM
Poster
LHW-plasma coupling and high density are two important issues in achieving LHCD H-mode plasma in EAST. Firstly, effects of LHW on the density at the grill mouth are investigated by a Langmuir probe installed in the top of the LHW antenna. Results show that the measured density with anti-clockwise Bt is lower than those with clockwise Bt, suggesting the asymmetric density behaviour in SOL....
Dr
Taina Kurki-Suonio
(Aalto University)
10/15/14, 8:30 AM
Poster
The new physics introduced by ITER operation, of which there is very little prior experience, is related to the very energetic (3.5 MeV) alpha particles produced in large quantities in fusion reactions. These particles not only constitute a massive energy source inside the plasma, but also present a potential hazard to the material structures that provide the containment of the burning plasma....
Dr
Pavel Aleynikov
(ITER Organization)
10/15/14, 8:30 AM
Poster
Runaway electrons (RE) can be generated during plasma disruptions in ITER. A large portion of the toroidal current can then be carried by RE, so that a substantial fraction of the magnetic energy would be associated with the RE current. The uncontrolled loss of such REs in ITER needs to be avoided to minimize the detrimental effects from disruptions. This calls for an adequate means to control...
Dr
Marina Kozintseva
(Moscow State Technical University of Radioengineering, Electronics and Automation, Moscow, Russia)
10/15/14, 8:30 AM
EXC - Magnetic Confinement Experiments: Confinement
Poster
The possibility of the creation of the magnetic system of multipole trap-Galatea on the basis of the levitating quadrupole from the superconducting coils-rings is considered. Based upon the superconductor property to conserve the trapped magnetic flux the analytical dependence of the potential energy of the proposed configurations from the coordinates of the levitating coils and the deflection...
Dr
Brett Chapman
(UW-Madison)
10/15/14, 8:30 AM
Poster
In MST plasmas where inductive current profile control routinely produces tokamak-like confinement with enhanced density and temperature gradients, a far-forward-collective-scattering diagnostic reveals a broadband reduction of density fluctuations, with as much as a 100-fold drop in amplitude. This drop is precipitated largely by the reduction of current-gradient-driven tearing modes....
Dr
Boris Bazylev
(Karlsruhe Institute of Technology, Germany)
10/15/14, 8:30 AM
Poster
The ITER Organization has recently decided to install a full-tungsten (W) divertor from the start of operations. One of the key issues with such a strategy is the possibility of W melting and melt splashing during transients, which can lead to modifications of surface topology and which may lead to higher disruption frequency or compromise subsequent plasma operation. Although every effort...
Dr
Florian Koechl
(Vienna University of Technology, Institute of Atomic and Subatomic Physics)
10/15/14, 8:30 AM
Poster
The dynamics of the access to and exit from high QDT regimes in the H-mode confinement regime in ITER is expected to be qualitatively different to present experiments: neutral fuelling is much less effective, Psep/PL-H < 2.0 even in stationary QDT ~ 10 burning conditions, the density evolution determines not only PL-H but also Palpha which in turn affects dWth/dt after a transition, and plasma...
Dr
Yueqiang Liu
(CCFE Culham Science Centre)
10/15/14, 8:30 AM
Poster
Three-dimensional external magnetic field perturbations, can either be intentionally applied such as in the experiments of mitigating edge localised modes (ELM) using resonant magnetic perturbations (RMP), or be un-intentionally generated such as the intrinsic error fields (EF). One crucial consequence of applying these (nearly) static 3D fields is the plasma flow damping.
In this work, we...
Dr
Laurie Porte
(CRPP-EPFL)
10/15/14, 8:30 AM
Poster
TCV is equipped with a suite of diagnostics capable of making fluctuation measurements of several plasma parameters. The suite has been used in a large variety of TCV discharges. Emphasis has been placed on the study of turbulence as a function of plasma shape and in particular of edge triangularity. Correlation ECE (CECE) measurements have shown that the relative electron temperature...
Prof.
Victor Vdovin
(NRC Kurchatov Institute)
10/15/14, 8:30 AM
Poster
The Innovative concept and 3D full wave code modeling Off-axis current drive by RF waves in large scale tokamaks, reactors FNSF-AT, ITER and DEMO for steady state operation with high efficiency is proposed. The scheme uses the helicons radiation (fast magnetosonic waves at high (20-40) IC frequency harmonics) at frequencies of 500-1000 MHz, propagating in the outer regions of the plasmas with...
Prof.
George N. Throumoulopoulos
(University of Ioannina)
10/15/14, 8:30 AM
Poster
We present recent results on steady states of translational symmetric and axisymmetric ITER relevant plasmas with incompressible sheared flow in connection with a generalized Grad-Shafranov equation and on their stability [1-2]. The presentation includes equilibria either with monotonically increasing safety factor profiles pertinent to the L-H transition or with reversed magnetic shear....
Mr
Vladislav Nesenevich
(Ioffe Physical-Technical Institute of the Russian Academy of Sciences)
10/15/14, 8:30 AM
Poster
One of the issues of the neutral particle diagnostics on ITER is to measure the distribution functions of the fast deuterium (D) and tritium (T) ions in MeV energy range. High energy tails in D,T-ion energy distributions (so-called knock-on ions) appear as a result of the close elastic collisions between the thermal fuel ions and the fusion alpha particles. The knock-on ion density depends...
Mr
Steven Sabbagh
(USA)
10/15/14, 8:30 AM
Poster
Favorable use of low magnitude (deltaB/B ~ O(10^-3)) three-dimensional (3D) magnetic fields in tokamaks includes mitigation of ELMs and Alfvénic modes, and alteration of the plasma rotation profile to strongly affect the stability of NTMs and RWMs. However, in ITER, these fields can significantly reduce the fusion gain, Q, by increasing alpha particle transport. These effects have been...
Dr
Andrey Bishaev
(Moscow State Technical University of Radioengineering, Electronics and Automation, Moscow, Russia)
10/15/14, 8:30 AM
EXC - Magnetic Confinement Experiments: Confinement
Poster
Quasi-stationary plasma confinement with a high β value was implemented in the Trimix-3M multipole magnetic trap. In the trap, magnetic surfaces of complex cross-section delimit a closed toroidal region with zero magnetic field at its center. The lifetime of the plasma in the trap is ~1 ms and the average value of β is ~0.35. The Rogowski loop is used to measure the value of the toroidal...
Dr
Yury Gribov
(ITER Organization)
10/15/14, 8:30 AM
Poster
This paper describes the progress in analysis of the ITER plasma vertical stabilization (VS) system since its Design Review 2007 – 2008. Two indices characterising plasma vertical stabilization were studied. These are 1) the maximum value of plasma vertical displacement due to free drift that can be stopped by the VS system and 2) the maximum Root Mean Square value of low frequency noise in...
Mr
Mark Nornberg
(USA)
10/15/14, 8:30 AM
Poster
Reversed Field Pinch (RFP) plasmas tend toward self-organized behavior depending on the nonlinear coupling between mutually interacting tearing modes. In multiple helicity plasmas one or more linearly unstable tearing modes may drive energy into stable modes through this coupling. In contrast, at high current and low density plasmas tend towards a state with a single dominant core mode....
Dr
Liang Wang
(Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP))
10/15/14, 8:30 AM
Poster
Divertor power and particle exhaust is a critical issue facing the operation of next-step fusion devices such as ITER and DEMO. Active control of excessive heat and particle fluxes under high power steady-state plasma conditions has become a frontier hotspot in magnetic confinement fusion development. Significant progress has been made in controlling transient and stationary divertor heat...
Dr
Basil Duval
(Ecole Polytechnique Fédérale de Lausanne – Centre des Recherches en Physique des Plasmas(CRPP), Association Euratom-Confédération Suisse(EPFL) CH-1015 Lausanne, Switzerland)
10/15/14, 8:30 AM
Poster
Dissipating the energy emitted from a fusion reactor remains critical to achieving a commercially viable design with acceptable machine lifetime. Using the extreme shaping capability of TCV together with an ‘open-vessel’ design, the Snowflake (SF) configuration divertor was first demonstrated on TCV. Although a nearly ‘exact’ SF configuration was obtained, most of this work concentrated on SF...
Mr
Mickey R. Wade
(USA)
10/15/14, 8:30 AM
Poster
Recent experiments with applied Resonant Magnetic Perturbations (RMPs) in low-collisionality ITER Similar Shape (ISS) plasmas on DIII-D have advanced the understanding of and increased confidence in obtaining ELM suppression in the ITER standard operating regime. ELM suppression is obtained with a reduced coil set (5–11 coils) on DIII-D, demonstrating the effectiveness of mixed harmonics...
Dr
Roger Reichle
(ITER Organization)
10/15/14, 8:30 AM
Poster
Dust and tritium inventories in the vacuum vessel have upper limits in ITER. Erosion, migration and re-deposition of wall material and co-deposition of fuel material are closely linked to the these inventories. The related suite of diagnostic and the respective set of plasma-wall-interaction physics related measurement requirements is now redefined as a whole because the decision to change...
Mr
Victor Zhogolev
(NRC "Kurchatov Institute")
10/15/14, 8:30 AM
Poster
During disruption mitigation by massive gas injection (MGI) the thermal energy is expected to be radiated with high efficiency in order to prevent excessive heat loads to first wall and divertor PFCs. The energy loss will take place in two phases: a) the so-called pre-thermal quench phase that lasts from the arrival of the first gas to the onset of increased transport due to MHD activity...
Dr
David Campbell
(ITER Organization)
10/15/14, 8:30 AM
Poster
The energy stored during a burning plasma pulse in ITER will significantly exceed that in present devices. Rapid release of this energy during a disruption has the potential to cause surface melting of plasma-facing components (PFCs) and will cause high electromagnetic loads, in some cases close to the design limits. Heat load specifications for ITER, which enter, for example, in the design...
Dr
Guoqiang Li
(Institute of Plasma Physica, Chinese Academy of Sciences)
10/15/14, 8:30 AM
Poster
This work extends previous BOUT++ work to systematically study the edge current driven kink mode, the effect of plasma shaping on the ELMs, to benchmark with other codes, and to validate the BOUT++ nonlinear ELM simulation on EAST tokamak experiments. A sequences of equilibrium with different edge current is generated with the CORSICA code, by keeping total current and pressure profile fixed....
Dr
Anatoly Mineev
(Joint Stock Company “D.V.Efremov Institute of Electrophysical Apparatus”)
10/15/14, 8:30 AM
Poster
The First Plasma operation is expected to be performed in ITER without blanket modules (with temporary limiters), with a toroidal magnetic field of 2.65 T at 6.2 m (half of the nominal value), starting from a partly charged central solenoid (producing half of the nominal poloidal magnetic flux). The First Plasma initiation will be more challenging in ITER than in present tokamaks. One reason...
Prof.
Xiang Gao
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/15/14, 8:30 AM
Poster
Pedestal turbulence was studied by a microwave reflectometry on EAST tokamak. The characteristics of edge pedestal turbulence during L-I-H transition, ELM-free H-mode phase and inter-ELM phase have been studied on EAST recently. (1) An edge spatial structure of density fluctuation and its dithering temporal evolution is observed on EAST tokamak during the L-H transition phase. (2) A coherent...
Mr
YoungMu Jeon
(Korea, Republic of)
10/15/14, 8:30 AM
Poster
As the most plausible technique to control the edge localized modes (ELMs) of high confinement mode (h-mode) plasmas, which is critical for ITER and beyond, non-axisymmetric resonant magnetic perturbations (RMPs) have been actively investigated in KSTAR. Since the first success of ELM suppression using n=1 RMPs in 2011 [1], our effort has been devoted to extend the operation regime of ELM...
Dr
Yongjian Xu
(Institute of Plasma Physics, Chinese Academy of Sciences)
10/15/14, 8:30 AM
Poster
As the first full superconducting non-circular cross section tokamak in the world, EAST is used to explore the forefront physics and engineering issues on the construction of tokamak fusion reactor. Neutral beam injection has been recognized as one of the most effective means for plasma heating. According to the research plan of the EAST physics experiment, two sets of neutral beam injector...
Prof.
XUEYU GONG
(Southwestern Institute of Physics)
10/15/14, 8:30 AM
Poster
A well-optimized design of an ion cyclotron resonance heating (ICRH) antenna is very important for steady-state plasma heating with high radio frequency (RF) power of several tens of megawatts. However, a sharp decrease in the coupling RF power because of impedance mismatch of ICRH system is an issue that must be resolved for present-day fusion reactors and International Thermonuclear...
Dr
Mike Kotschenreuther
(University of Texas)
10/15/14, 8:30 AM
Poster
We show that X-Divertors (XD), that mainly expand magnetic flux near the SOL peak heat flux strike point on the divertor plates, can be created for ITER, many existing tokamaks (e.g., SST-1, EAST, AUG, … ), and future Reactors (KDEMO, ARIES) without modifying their Poloidal Field (PF) coil sets (or adding internal coils). For ITER, KDEMO, SST-1, and EAST, we will present sequences of XDs,...
