Prof.
Jorge Alberto González Guevara
(Universidad Autónoma de Nuevo León)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
An important system into the magnetic confinement devices to obtain appropriate knowledge on plasma behavior in nuclear fusion is the electron cyclotron resonance heating (ECRH). We present the preliminary design of our source for ECRH system applied in our Tokamak device, a gyrotron device 60 GHz-300 kW which is currently developed by the Fusion Research Group (GIF, Spanish acronyms) at the...
Dr
Ronald E. Waltz
(General Atomics)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Local nonlinear gyrokinetic code GYRO [1] simulations of energetic particle driven low-n Alfven eigenmodes embedded in high-n microturblence have motivated a local critical gradient model (CGM) for stiff energetic particle (EP) transport from Alfven eigenmodes (AEs). The critical gradient in the EP density (or pressure) gradient identified by the local linear low-n AE growth exceeding the...
Dr
Yuri Petrov
(CompX)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The finite-difference bounce-average Fokker-Planck (FP) code CQL3D [R.W. Harvey and M. McCoy, "The CQL3D Fokker Planck Code"] has been upgraded to include the Finite-Orbit-Width (FOW) effects. This is achieved by transforming the FP equation written in canonical action variables to another set of Constant-Of-Motion (COM) coordinates. A distinctive feature of our approach from that used by...
Dr
Makoto Sasaki
(Research Institute for Applied Mechanics Kyushu University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A new branch of geodesic acoustic modes (GAMs) driven by the magnetic drift motion of fast ions is presented. An effective ion heating mediated by the new branch is expected. Strong ion Landau damping is attributed to the eigenfunction of the new branch, which has steep poloidal gradients. The analysis is based on a gyrokinetic model. The gyrokinetic equation for the fast ions has two kinds of...
Dr
James Myra
(Lodestar Research Corporation)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Heating and current drive by ion cyclotron range of frequency (ICRF) waves is expected to play an increasingly important role as tokamak research progresses towards the reactor regime. The basic heating and current drive interactions of ICRF waves with the core plasma are well understood, and sophisticated modeling tools are available. In contrast, the ability to understand, predict and...
Dr
Hyun-Seok Kim
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Advanced tokamak operations, promising candidates for DEMO operations, require control of plasma profiles to establish and to sustain the enhanced energy confinement and the non-inductive current fraction. The safety factor (q) profile and the electron temperature (Te) profile control have to be controlled to access and maintain the advanced operation modes and to improve controllability of...
Christian Day
(KIT)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The JT-60SA device will start operation in 2019. One of the top research goals is to study high density plasma physics in view of a demonstration fusion power plant. In this context, this paper presents an integrated modelling of the divertor pumping system of JT-60SA.
The paper first presents a generic integrated workflow to assess the operational window of the pumping system. This approach...
Dr
Jun Gyo Bak
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The investigation of poloidal halo current (HC) Ih flowing along the support structures for plasma facing components (PFCs) during the vertical displacement event (VDE) under the toroidal magnetic field BT is required for the estimate of Ih x BT force on the structures in the KSTAR tokamak because it can be expected that the force will cause damages on the structures in the KSTAR when plasma...
Dr
Kimin Kim
(Korea Advanced Institute of Science and Technology)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Toroidal rotation braking by neoclassical toroidal viscosity driven by non-axisymmetric (3D) magnetic fields, called magnetic braking, has great potential to control rotation profile, and thereby improve tokamak stability and performance. In order to characterize magnetic braking in various 3D field configurations, dedicated experiments have been carried out in 2015 campaign, applying a...
Dr
John Berkery
(Columbia University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A comprehensive approach to the prevention of disruption of fusion plasmas in tokamaks begins with identifying disruption event chains and the specific physics elements which comprise those chains. Then, if the events in the disruption chains can be forecast, cues can be provided to an avoidance system to break the chain. Within this framework, we examine the characterization and forecasting...
Mr
Min-Keun Bae
(Hanyang University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Although Type I ELM heat flux mainly reaches the divertor plates, it would cause severe damage to the first wall in advanced tokamaks due to radial convective loss of ELM. Heat loads on the first wall is mostly caused by the fast radial convective propagation of ELM filaments. In this paper, heat fluxes toward the first wall of KSTAR device are investigated as a form of ELM filaments, and they...
Dr
Rajesh Maingi
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Experiments in NSTX demonstrated reproducible operation with inter-discharge lithium evaporation, eliminating the need for inter-discharge helium glow discharge cleaning (HeGDC), improving plasma confinement as well as the duty cycle. To assess the viability of operation without HeGDC and directly compare with inter-discharge lithium evaporation, the inter-discharge HeGDC duration was...
Dr
Suk-Ho Hong
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In this paper, we report the results from a series of experiment using special tungsten block tiles performed in KSTAR on fuel retention inside the gap of castellated blocks of different shapes. Results presented in this paper suggest a comprehensive understanding on deposition procedure inside the gap and would give valuable information on the Be deposition inside the gap of castellated...
Mr
Phani Kumar Domalapally
(Research Centre Rez)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Determination of the likely heat loads which may be expected on the First Wall (FW) of the projected European fusion reactor DEMO is still underway. This uncertainty notwithstanding, the engineering design of the heat sink components must proceed, hence the scientific community is using the so called bottom-up approach to determine the maximum heat flux that the component could sustain given...
Mr
Stephen Manuel Manoah
(Institute for Plasma Research, Gandhinagar, Gujarat-382428, INDIA)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ITER presents the most demanding challenge to Remote Handling (RH) operation ever in terms of weight, complex geometry, limited space, required accuracy and task quality level. The ITER in-vessel components are to be maintained or replaced remotely since these components will be activated by high energy neutrons. In order to perform the in-vessel RH maintenance tasks, an RH system known as...
Prof.
Göran Ericsson
(Applied Nuclear Physics, Dept of Physics and Astronomy, Uppsala University, Uppsala Sweden)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The proposed High Resolution neutron Spectrometer (HRNS) system for ITER is composed of a suite of neutron spectrometers with the primary function to provide measurements of the fuel ion ratio, nT/nD, in the plasma core. Supplementary functions are to assist or provide information on fuel ion temperature, Ti, energy distributions of fuel ions and confined alpha-particles and neutron emission...
Mr
Carl Hellesen
(Uppsala University)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Measurements of the core plasma fuel ion density ratio (nT/nD) is required for safe and efficient burning plasma operations at ITER. However, this measurement is difficult and very few working techniques have been demonstrated. One candidate method to obtain the fuel ion composition is Neutron Emission Spectroscopy, specifically, measurement and analysis of the DT neutron spectrum of neutral...
Dr
Massimo Nocente
(Department of Physics, ItUMiB)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Among the key goals of ITER are the investigation of alpha particle physics in a burning plasma as well as the demonstration of the control of runaway electrons born in disruptions. The diagnostic needs to meet these goals are the determination of the alpha particle profile with a time resolution of < 0.1 s and the evaluation of the runaway electron beam current and end point energy with an...
Mr
Nikolai Bakharev
(Ioffe Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
For the first time a high energy counter-NBI was applied in the Globus-M spherical tokamak. The ELM-free H-mode was obtained. However no significant increase in the ion temperature and plasma energy content as compared to ELMy H-mode was observed. This is due to a high level of the fast ion losses (up to 97%), confirmed by modeling with NUBEAM and full 3D fast ion tracking algorithm. Increase...
Dr
Elena Belova
(PPPL)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
An energy channeling mechanism is proposed to explain flattening of the electron temperature profiles at high beam power in beam-heated National Spherical Torus Experiment (NSTX). High-frequency Alfvén eigenmodes are frequently observed in beam-heated NSTX plasmas, and have been linked to enhanced thermal electron transport and flattening of the electron temperature profiles. Results of 3D...
Dr
Jinseok Ko
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The current profile evolutions have been measured from the plasma discharges with the electron cyclotron current drive (ECCD) for the Korea Superconducting Tokamak Advanced Research (KSTAR) for the first time. This measurement has been possible by the newly-installed motional Stark effect (MSE) diagnostic system that utilizes the polarized Balmer-alpha emission from the energetic neutral...
Aleksandr Zvonkov
(Project Center ITER)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
CXRS diagnostics supply a set of important plasma parameters of fusion plasmas. According to the system requirements, the CXRS diagnostics in ITER should supply plasma velocity (poloidal and toroidal), impurity ion densities and ion temperatures. The ITER CXRS-edge diagnostic system must measure these parameters over the outer half of the plasma radius.
The use of CXRS in ITER encounters...
Dr
Kiyoshi Itami
(Japan Atomic Energy Agency)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Advanced design for Divertor Impurity Monitor (DIM) and IR Thermography (IRTh) is being developed in Japan to contribute to the divertor plasma control and research in ITER through the spectroscopic measurement with high spatial and spectral resolutions and accurate measurement of the target temperature.
DIM spectroscopically (200 nm – 1000 nm) measures two dimensional profiles of the...
Mr
Shrishail B Padasalagi
(ITER-India, Institute For Plasma Research)
19/10/2016, 14:00
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...
Dr
Koji Takahashi
(Japan Atomic Energy Agency)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ITER EC equatorial launcher (EL) has been newly designed to achieve an enhanced electron cyclotron current drive performance based on the dedicated calculations. The millimeter(mm)-wave beam design of EL optimized the mm-wave transmission capability and spatially limited beam path such as the mirrors' dimension and the plug mounted Blanket Shield Module openings has implemented poloidal...
Mr
Naotaka Umeda
(Japan Atomic Energy Agency)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Dc ultra-high voltage insulation technologies in oil, gas and vacuum have been newly developed to fabricate dc 1MV power supply components in the neutral beam (NB) system on ITER. In the ITER NB system, a 1 MV power supply with output pulse duration of 3600 s is required, which is twice higher in the voltage and two orders longer in the pulse than those of the existing NB system in the world....
Dr
Ricardo Farengo
(Comision Nacional de Energia Atomica)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Theoretical calculations and particle simulations are used to show that charge changing processes (i.e. charge exchange) can significantly increase the diffusion of alpha particles in the pedestal-edge-SOL regions. The interaction of the alpha particles with the plasma species, He+ and neutral deuterium (both atomic and molecular) and helium are included. The numerical code calculates the...
Dr
Jayhyun Kim
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
It has been regarded that magnetic perturbation (MP) by non-axisymmetric fields is the most promising technique in controlling edge localized mode (ELM) crashes that are potentially harmful to the lifetime of first wall in reactor scale devices. However, the exact mechanism of MP has not been fully understood in both ELM crash mitigation and suppression. Here, we investigated the...
Mr
Jeongwon Lee
(Seoul National University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
ECH-assisted plasma start-up using trapped particle configuration (TPC) is performed in KSTAR 2015 experiment campaign for feasibility study of TPC in superconducting, conventional tokamaks. It is widely known that ECH can significantly assist the start-up of tokamak plasmas with pre-ionization. The dependency of the quality of the ECH pre-ionization plasma on the magnetic configuration has...
Dr
Shin Kajita
(Nagoya University)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Reflection of light on walls will form parasitic signal on various diagnostics and be a serious issue in ITER. In this study, we show the recent progress in the assessment of the effects of the wall reflections in ITER on visible spectroscopy, Thomson scattering, active spectroscopy, and infrared thermography based on the ray tracing simulation modeling. In this study, it is shown that the...
Mr
Joohwan Hong
(Korea Advanced Institute of Science and Technology)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Experiments were conducted in KSTAR plasmas by injecting a trace amount of Ar gas as a test particle while applying two different actuators: electron cyclotron resonance heating (ECH) and resonant magnetic perturbation (RMP). Effects of ECH was investigated in KSTAR L- and H-mode discharges. For L-mode discharges (I_p = 400 kA, B_t = 2 T), 110 GHz ECH of 350 kW was applied to heating positions...
Mr
ARUN KUMAR CHAKRABORTY
(ITER-India, Institute for Plasma Research, Bhat Gandhinagar – 382428, India)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Beam Source (BS) for Neutral Beam Injectors consists of two parts: “ion source” and “accelerator system”. For the ITER Diagnostic Neutral Beam (DNB), the ion source is the plasma generator and consists of eight inductively coupled Radio Frequency (RF) plasma drivers. The accelerator system consists of three grids and accelerates the negative ion beam to 100 keV. The three grids: plasma...
Dr
Francesca Poli
(PPPL)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Among the external heating systems planned in ITER, the Electron Cyclotron system has the highest flexibility. By combining the equatorial and the upper launcher, the EC can cover the whole plasma radius, from the axis to the edge, allowing for combined central heating, current profile tailoring and MHD stability control.
This work discusses how to best use the EC system in synergy with the...
Dr
Michael Bongard
(University of Wisconsin-Madison)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Operation in the high confinement (H-mode) regime and mitigation of associated deleterious Edge Localized Mode (ELM) activity are necessary for the success of ITER and future reactors. H-mode studies at near-unity aspect ratio A can offer unique insights into these issues. Edge plasma parameters at low A permit unique measurements of the edge pedestal with high spatiotemporal resolution using...
777.
ELM, Edge Turbulence and Their Interaction in the ELM-crash Suppression Phase under the n=1 RMP
Dr
Jaehyun Lee
(Ulsan National Institute of Science and Technology)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The effect of static n=1 resonant magnetic perturbation (RMP) on edge-localized mode (ELM) and edge turbulence has been investigated using electron cyclotron emission imaging (ECEI) system. The ECEI revealed that filamentary ELM is still present in the edge when the ELM crash is completely suppressed by n=1 RMP. Correlation analysis showed the RMP enhances turbulent fluctuations in the edge...
Dr
Junghee Kim
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Energetic ions generated by auxiliary heating and fusion reactions are able to produce the characteristic Alfvenic activities such as excitation of Alfvén eigenmodes (AE) and high-frequency chirping modes through wave-particle interactions. In KSTAR on-axis neutral beam injection (NBI) is a main supplier of the fast ions, and has two primary roles which are heating and current drive. Beam-ions...
Dr
Yang Ren
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Plasma turbulence is considered one of the main mechanisms for driving anomalous thermal transport in magnetic confinement fusion devices. Based on first-principle model, gradient-driven gyrokinetic simulations have often been used to explain turbulence-driven transport in present fusion devices, and in fact, many present predictive codes are based on the assumption that turbulence is...
Dr
Si-Woo Yoon
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
For the realization of the fusion reactor, solving issues for high beta steady-state operation is one of the essential research topics for the present superconducting tokamaks and in this regard KSTAR has been focusing on maximizing performance and increasing pulse length addressing scientific and technical issues. Typically, previous study on high beta operation has been focusing on advanced...
Dr
Masayuki TOKITANI
(JpNIFS)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
It is considered that copper alloy could be used as a divertor cooling tube in not only helical reactor FFHR-d1 but also tokamak DEMO reactor, because of utilizing its high thermal conductivity. This study focused on using an oxide dispersion strengthened copper alloy (ODS-Cu) of GlidCop® (Cu-0.3wt%Al2O3) as the divertor heat sink material of FFHR-d1. This alloy has superior high temperature...
Dr
Mark Boyer
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Spherical torus based designs for fusion nuclear science facilities [1] and pilot plants [2] have little to no room for a central solenoid, and require the plasma current to be generated non-inductively. Recently completed upgrades to NSTX-U will enable the study of non-inductive scenarios, including start-up, ramp-up, and flattop current sustainment. This paper examines active control of such...
Dr
Antonis Sergis
(Imperial College London, CCFE)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
HyperVapotrons (HVs) are highly robust and efficient heat exchangers able to transfer high heat fluxes of the order of 10-20MW/m2. They employ the Vapotron effect, a complex two phase heat transfer mechanism, which is strongly linked to the hydrodynamic structures present in the coolant flow inside the devices. HVs are currently used in the Joined European Torus (JET) and the Mega Amp...
Dr
Yuejiang Shi
(Seoul National University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In KSTAR experiments, we found that non-local transport (NLT) is closely connected to the rotation reversal and impurity transport. We demonstrated that NLT can be controlled by ECH, and the intrinsic rotation and impurity dynamics follow the change in NLT. Supersonic molecular beam injection (SMBI) was used to induce the cooling of edge electrons. The cut-off density for NLT can be...
Dr
Pavel Aleynikov
(Max-Planck-Institut für Plasmaphysik)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A consistent description of runaway electron (RE) generation in plasma disruptions remains an open physics issue. The possibility of the formation of high post-disruption RE currents raises safety-related concerns for large tokamaks, such as ITER. Although the avalanche mechanism of RE production is anticipated to be the dominant mechanism in ITER [M.N. Rosenbluth, S.V. Putvinski, Nucl. Fusion...
Dr
Donald Spong
(Oak Ridge National Laboratory)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Instabilities driven by energetic particle (EP) components are of interest to magnetic fusion concepts since they can lead to decreased heating efficiency, high heat fluxes on plasma-facing components, and decreased ignition margins in reactor systems. Since 3D magnetic field perturbations will be present to some extent in all toroidal configurations, the analysis of EP instabilities in 3D...
Prof.
Wenlu Zhang
(CnCASIOP)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The fast electron driven beta induced Alfven eigenmode (e-BAE) has been routinely observed in HL-2A tokamak. We study e-BAE for the first time using global gyrokinetic GTC simulation, where the fast electrons are described by the drift kinetic model. Frequency chirping is observed in nonlinear simulations in the absence of sources and sinks, which provide a new nonlinear paradigm beyond the...
Dr
Hyungho LEE
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Divertor target heat loads in future long pulse, high power tokamak reactors such as ITER or DEMO will impose major operational constraints. Detached divertor operation and suppression or substantial mitigation of Edge Localized Modes (ELMs) will be mandatory. One of the most promising ELM mitigation methods to be applied on ITER is the use of 3D magnetic perturbations (MPs). This technique...
Dr
James Anderson
(General Atomics)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER ECH transmission lines have challenging-to-meet transmitted waveguide mode purity requirements, pushing individual subcomponents towards strict manufacturing tolerances. In addition, most ECH components will require active cooling to remove heat generated by microwave losses, even those with very high transmission efficiencies. To meet these two particular challenges, several new...
Dr
Thomas Jenkins
(Tech-X Corporation)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The heating of confined tokamak plasma to fusion-relevant temperatures can cause sputtering of high-Z impurities from plasma-facing components, and such impurities radiatively cool the plasma, especially as transport effects carry them to the reactor core. The sputtering process is believed to be exacerbated by the large electromagnetic fields generated by RF antennas, since these fields...
Dr
Hideya Nakanishi
(National Institute for Fusion Science)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A high-performance data transfer method has been developed for full data replication between ITER and the remote experimentation centre (REC) in Japan for the first time. Fast data transfer technology has been investigated as the crucial activity of REC with F4E, JAEA, NIFS, and NII collaboration. Full replication of ITER data will be expected to provide not only an equivalent research...
Dr
Guoyong Fu
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Energetic particle modes and Alfvénic modes driven by super-Alfvénic beam ions were routinely observed in neutral beam heated plasmas on the National Spherical Torus Experiment (NSTX). These modes can significantly impact beam-ion transport, thus causing beam-ion redistribution and losses. In this paper we report on new self-consistent hybrid simulations of both fishbone instability and TAEs...
Dr
David Smith
(University of Wisconsin-Madison)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Characteristic edge localized mode (ELM) evolution patterns are identified and measured at Alfven timescales with a multi-point beam emission spectroscopy (BES) diagnostic on NSTX/NSTX-U, and parameter regimes corresponding to the characteristic ELM evolution patterns are identified. The linear peeling-ballooning stability boundary expresses an onset condition for ELMs, but ELM saturation...
107.
Improving fast-ion confinement in high-performance discharges by suppressing Alfve´n eigenmodes
Mr
Gerrit J. Kramer
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The performance of steady-state DIII-D discharges is often reduced due to anomalous fast-ion
transport that was observed to correlate with Alfv´en eigenmode (AE) activity. Fast-ion transport
modeling using the kick model [1] shows that the observed mode activity can account for the
observed fast-ion confinement degradation. Therefore, suppressing the AE activity will improve
the plasma...
Dr
Won Ha Ko
(Korea, Republic of)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Significant reduction of H-mode power threshold (P_th) has been identified in KSTAR. Such a favorable finding is attributable to low intrinsic error field [1] and toroidal field ripple[2], which has been corroborated by high pedestal rotation. According to a preliminary comparison, KSTAR has at least 10% lower Pth during L to H-mode transition than DIII-D which have similar size but with...
Dr
Syun'ichi SHIRAIWA
(PSFC, MIT)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A new efficient full wave simulation approach to solve a driven RF waves problem in hot core and edge SOL plasmas self-consistently is presented. Existing RF simulation codes are integrated to reconstruct self-consistent solutions from solutions obtained from each code. The approach allows for treating hot core plasma, SOL plasmas and launcher structure self-consistently, incorporating...
Prof.
Kazuaki Hanada
(Advanced Fusion Research Center, Research Institute for Applied Mechanics, Kyushu University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Hydrogen (H) recycling and wall pumping properties on a dynamic retention dominant wall (metal wall) have been investigated in a medium size spherical tokamak QUEST. The plasma facing wall on QUEST originally made of stainless steel type 316L (SS316L) and partially coated by atmosphere plasma splay tungsten has been already covered with re-deposition layer of 5-100 nm in thickness due to...
Dr
Hiroshi Tanabe
(University of Tokyo)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
We present results of recent studies of merging/reconnection heating during central solenoid (CS)-free plasma startup in the Mega Amp Spherical Tokamak (MAST) which achieved major progress in the last three years through the use of new 32 chord ion Doppler tomography, 130 channel YAG- and 300 channel Ruby-Thomson scattering diagnostics. In addition to the previously achieved ~1keV heating...
Dr
Young-Seok Park
(Columbia University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
H-mode plasma operation in KSTAR reached high normalized beta, beta_N, up to 4.3 with reduced plasma internal inductance, l_i, to near 0.7. This significantly surpassed the computed n = 1 ideal no-wall beta_N limit by a factor of 1.6. The high beta_N above 4 has been achieved in discharges having lowered B_T in the range 0.9-1.3 T with plasma current of 0.35-0.43 MA. The l_i was maintained at...
Dr
Woochang Lee
(UNIST)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In KSTAR L-mode discharges (B_t0 = 3−3.3 T and I_P = 600 kA) heated by ~1.5 MW neutral beam injection (NBI), 200−400 kHz turbulent fluctuations were observed with a multichannel (4 radial and 16 poloidal) microwave imaging reflectometer system [1]. Linear gyrokinetic simulations with GYRO predicted that turbulence is most unstable at k_theta ~ 3 /cm (k_theta rho_s ~ 0.4) and the most unstable...
Dr
Steven Sabbagh
(Columbia University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Neoclassical Toroidal Viscosity (NTV) due to non-ambipolar particle diffusion occurs in tokamaks due to low magnitude (dB/B0 ~10-3) three-dimensional (3D) applied magnetic fields, used for positive purposes including alteration of the plasma rotation profile, Vt, to stabilize MHD modes and for ELM suppression. As ITER and future devices will use 3D fields for these purposes, it is important to...
Dr
Aihui Zhao
(Tsinghua University, China)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The lower hybrid current drive (LHCD) is one of the most effective tools for driving current in present tokamak plasmas. However, for reactor-graded density plasmas, the efficiency of LHCD degrades dramatically. The dependence of LHCD efficiency on isotopic plasma content (hydrogen/deuterium) was studied in experiments. Although according to the linear dispersion theory, the deuterium plasma...
Dr
Eugene Mukhin
(Ioffe Institute)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Measuring electron temperature and density profiles is а high priority task for tokamak diagnostics because the electron component is one of the main channels for the anomalous
power loss and it is strongly sensitive to transient processes in the tokamak plasma. The Core TS in ITER must cover the whole core region r/a < 0.85, R > 6 m with a spatial resolution of 67 mm or better and must be...
Prof.
Yuji Hatano
(Hydrogen Isotope Research Center, University of Toyama)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The goal of the Japan-US joint research project PHENIX (2013–2018) is to understand the feasibility of He-cooled W divertor for DEMO applications. To achieve this goal, the project has three major objectives: (1) to understand heat transfer in a divertor module cooled with high-temperature and high-pressure He gas, (2) to establish database on thermomechanical properties of W materials after...
Prof.
Tünde Fülöp
(Chalmers University of Technology)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Runaway electrons (REs) are a pressing issue for ITER due to their significant potential to cause damage. Improved knowledge of RE formation mechanisms, their dynamics and characteristics, as well as transport or loss processes that may contribute to RE suppression and control, will benefit the fusion community and contribute to a safe
and reliable operation of reactor-scale tokamaks.
In...
Mr
Filippo Scotti
(LLNL)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The response of kinetic plasma profiles to 3D-field triggered edge localized modes (ELMs) and the inter-ELM carbon impurity transport were analyzed in lithium-conditioned H-mode discharges in NSTX. ELM-free lithium-conditioned H-mode discharges were characterized by core accumulation of impurities as a result of near-neoclassical impurity transport, an edge inward pinch and the absence of...
Dr
Alexey Arefiev
(Institute for Fusion Studies, University of Texas at Austin, USA)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
High-performance spherical tokamaks are usually overdense, so regular electron cyclotron emission is blocked. However, electron Bernstein waves, generated at the local cyclotron frequency (and its harmonics) in the core may be observed outside the plasma via a mode conversion process that takes place typically in the plasma edge between an electromagnetic mode and the (electrostatic) electron...
Rory Perkins
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
We propose a new model for the anomalous loss of high-harmonic fast-wave (HHFW) heating power to the scrape-off layer (SOL) of the National Spherical Torus eXperiment (NSTX). A significant fraction, up to 60%, of the coupled HHFW power can be lost along scrape-off layer field lines [1], creating bright spirals of heat deposition on the upper and lower divertor regions [2]. It is important to...
Dr
Gregorio Vlad
(ENEA, Dipartimento FSN, C.R. Frascati, Italy)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Internal kink instabilities exhibiting fishbone like behaviour have been observed in a variety of experiments where a high energy electron population, generated by strong auxiliary heating and/or current drive systems, was present. Numerical simulations using XHMGC, a hybrid MHD-Gyrokinetic code, has been already applied successfully to analyses of modes driven by energetic electrons. In...
Dr
Mikhail Modestov
(Princeton University/Nordita)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Successful design of liquid metal wall or divertors for nuclear fusion reactors require the understanding of the behavior of liquid metal flows. The Liquid Metal eXperiment (LMX) at PPPL has been designed in a form of a rectangular channel allowing investigation of major issues of heat transfer and magnetic field influence relevant to tokamak divertor operation. We present the numerical...
Dr
Luis F. Delgado-Aparicio
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A simple heating technique has been developed that could provide an actuator to circumvent error-field-induced locked-mode disruptions in tokamak plasmas. New observations of the formation and dynamics of error-field-induced locked-modes at ITER toroidal fields, without fueling and external momentum input have recently been carried out on Alcator C-Mod. Locked-mode excitation is achieved by...
Dr
Sang Gon Lee
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Highly coherent structures associated with an extremely long-lived saturated magnetohydrodynamic (MHD) instability have been observed in KSTAR tokamak under a long-pulse and steady-state operation. As the plasma performance is increased in advanced tokamak regimes, possible deleterious effects of MHD modes become more important, especially for steady-state burning plasmas in the next-step...
Dr
MunSeong Cheon
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Recently it is suggested that the loss of runaway electrons localized in the plasma triggers the plasma disruption by transferring their energy to the first wall generating massive impurities, based on the observation in KSTAR. In order to check the feasibility of the suggestion, localized magnetic perturbation was applied on the plasma edge to remove runaway electron beam from the plasma,...
Prof.
Evgeniy Gusakov
(Ioffe Institute)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A model interpreting generation of the anomalous backscattering signal in the second harmonic X-mode ECRH experiments at TEXTOR as a secondary non-linear process, which accompanies a primary low – threshold parametric decay instability (PDI) leading to excitation of two–upper hybrid (UH)–plasmon trapped in plasma is introduced. The primary absolute PDI enhancing the UH wave fluctuations from...
Mr
Arunkumar Chakraborty
(ITER-India, Institute for Plasma Research, Bhat, Gandhinagar – 382 428, Gujarat, India)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Indian Test Facility (INTF) is designed for “Full characterization of the Diagnostic Neutral Beam (DNB)” for ITER, to unveil the possible challenges in production, neutralization and transportation of neutral beam over the path length of ~20.67m. This facility consist of a vacuum vessel (of volume >180m3) which has been designed and manufactured as per ASME Sec.VIII Div. 1, to house and...
Dr
Kwan Chul Lee
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
An analysis of edge density evolution during the large ELMs on KSTAR is developed by the measurements including two interferometer systems and the Beam Emission Spectroscopy (BES). The vertical Far Infra-Red interferometer (FIRI) data of large ELM crashes for the high power heated plasma showed plasma density increase, which is a contrary tendency to the general plasma density change at the...
Dr
Sang-hee Hahn
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The paper summarizes a series of multi-year experimental activities done under the ITPA MHD stability TG from year 2012 to year 2015. The relevant activity, MDC-18, addresses many axisymmetric control issues needing resolution for ITER, which include 1) fundamental controllability of axisymmetric equilibria and relevant metrics, 2) effect of noise in the principal diagnostics and 3) evaluate...
roberto zanino
(dipartimento energia, politecnico di torino)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Solutions for the steady-state power exhaust problem in future fusion reactors (e.g, DEMO) are not automatically provided by present experiments or even ITER, because the expected heat fluxes, as well as the level of neutron irradiation, will be much higher. Dedicated work packages are being devoted to this problem within EUROfusion and even a dedicated facility (the Divertor Tokamak Test –...
Dr
Hiroshi Idei
(Research Institute for Applied Mechanics, Kyushu University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
By means of dual 8.2 GHz and 28 GHz waves, the over dense 25 kA plasma with central high energetic-electron pressure was non-inductively built up and sustained for 0.4 s by Electron Bernstein Wave Heating (EBWH) effect between 8.2 GHz fundamental and 2nd harmonic Electron Cyclotron (EC) layers. Spontaneous Density Jumps (SDJs) have been clearly observed at a few times in a shot, and the...
Prof.
Hitoshi Tanaka
(Kyoto University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Extremely overdense spherical tokamak plasmas are produced non-inductively with electron Bernstein waves mode-converted via O-X-B scheme. When the fundamental electron cyclotron resonance (ECR) layer is located at the plasma core and the 2nd harmonic ECR layer is near the outboard vessel wall and the upper hybrid resonance layer is located between them, significant density rise is obtained...
Dr
Zhiyong Qiu
(Zhejiang University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Theory of low-frequency zonal structure (LFZS) generation as one mechanism for Alfvén eigenmode (AE) nonlinear saturation is presented, including 1) spontaneous excitation of LFZS by beta-induced AE (BAE) via modulational instability, and 2) effects of energetic particles (EPs) on zonal flow (ZF) generation by Toroidal AE (TAE). It is found that, LFZS can be driven by a finite-amplitude BAE...
Dr
Maxime Lesur
(FrIJR)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Energetic ions in fusion plasmas can excite the Geodesic-Acoustic Mode (GAM), which is a finite-frequency counterpart of zonal flow. Depending on plasma conditions, GAMs can significantly enhance or mitigate transport. Therefore, understanding and controlling their excitation is of great interest. Recent observations on the LHD have revealed a new phenomenon of abrupt excitation of...
Zhihong Lin
(UC Irvine)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In this paper, we report gyrokinetic simulations of nonlinear interactions between beta-induced Alfven eigenmode (BAE) and beta-induced Alfven-acoustic eigenmode (BAAE), low frequency modes that have strong interactions with both thermal and energetic particles. When the ion temperature is comparable to the electron temperature, the unstable BAAE can be excited by realistic energetic particle...
Mr
Jian Bao
(Peking University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In this work, we present a fully nonlinear electromagnetic particle simulation model for RF wave in the toroidal geometry, which has been successfully implemented in the gyrokinetic toroidal code (GTC). In this electromagnetic simulation model, the ion dynamics is described by 6D Vlasov equation and the electron dynamics is described by 5D drift kinetic equation. The ion cyclotron orbit is...
Prof.
Chang-Mo Ryu
(POSTECH)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Toroidicity induced Alfven eigenmodes (TAE) [1-3] can be driven unstable by fast particles from neutral beam heating or fusion reactions and have been observed in different tokamaks [4-5]. We report the observation of TAEs in KSTAR plasmas during the 2013-2015 campaigns by the fast particles produced the neutral beam injection and global gyrokinetic simulations of them by using the GTC and...
Prof.
Liu Chen
(Zhejiang University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Zonal flow (ZF) and zonal current (ZC) in fusion devices are manifestations of ,respectively, electrostatic (ESCC) and magnetostatic (MSCC) convective cells in uniform plasmas. Similarly, kinetic Alfv´en waves (KAW) appear as kinetic Alfv´en eigenmodes (KAE) due to the presence of Alfv´en continuum. Employing this paradigm, we have investigated the spontaneous excitation of CC via modulational...
Dr
Dmitry Gin
(RuIoffe)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Gamma ray spectrometry (GRS) is a mature technique implemented on many past and present tokamaks, including EAST, TFTR, JET etc. that can provide detailed data on the distribution functions (DF) of the plasma fast particles.
In several stages it was undertaken a fusion plasma gamma emission sources (GES) study. Firstly, data on main reactions relevant to alpha particles diagnostics were...
Dr
Xin Wang
(Max-Planck-Institut für Plasmaphysik, Boltzmannstraße 2, Garching D-85748, Germany)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Shear-Alfvén modes can be driven unstable by energetic particles (EPs) produced by additional heating or nuclear fusion reactions. Alfvénic fluctuations can, in turn, be derimental to EP confinement and lead large EP losses. Understanding the properties of EP confinement largely depends on the insights into Alfvén mode dynamics, with regard to both the linear stability properties; and the...
Dr
Yasunori Kawano
(Japan Atomic Energy Agency)
19/10/2016, 14:00
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. Highlights of the Topical Group activity focus on: (1) mitigating degradation of first mirrors in optical systems, development of techniques for removing impurity deposition on mirrors; (2) characterization of in-vessel...
Prof.
Zhe Gao
(Tsinghua University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Generation of plasma toroidal flow without or with low momentum input has been attracted much attention due to the key issue of plasma rotation on MHD stabilization and turbulence regulation. The general momentum equation is reached with a generalized ponderomotive force and then the drive and transport of parallel momentum are discussed in the case of rf injection and/or in the drift-wave...
Eric Fredrickson
(PPPL)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The International Tokamak Experimental Reactor (ITER) will have a large population of non-thermal, energetic ions consisting of fusion generated alphas and beam ions injected for current profile control. Potential redistribution and/or loss of those non-thermal ions is thus of concern as it will modify heating profiles, current profiles, and could lead to unacceptable levels of heating of...
Dr
Larry R. Baylor
(Oak Ridge National Laboratory)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The formation and acceleration of cryogenically solidified pellets of hydrogen isotopes has long been under development for fueling fusion plasmas. Injectors are being designed to provide this capability for fueling ITER with DT pellets injected from the inner wall. In addition to the fueling application, smaller pellets of D2 are to be injected from the outer or inner wall to purposely...
Dr
Akira Ejiri
(Graduate School of Frontier Sciences, The University of Tokyo)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Plasma start-up without a large flux swing central solenoid (CS) is one of critical issues in fusion research. In the TST-2 spherical tokamak (ST), non-inductive start-up by waves in the lower-hybrid frequency range (200 MHz) has been studied using three types of antennas. Presently a capacitively-coupled combline (CCC) antenna is used. The maximum sustained plasma current was increased from...
Mr
Shrishail B Padasalagi
(ITER-India, Institute for Plasma Research)
19/10/2016, 14:00
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 environment for components operating in the range from 4.5 k to 80 k like ITER vacuum vessel and the superconducting magnets. The Cryostat is divided into four section, of which, Base section is most complex because of its web shaped structure sandwiched between two 60mm thick plates with...
Dr
Yuanlai Xie
(Institute of Plasma Physics,Chinese Academy of Sciences)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The neutral beam injection system of EAST (EAST-NBIS) consists of two sets of neutral beam injectors (namely EAST-NBI-1 and EAST-NBI-2). Each of them has two ion sources which can operate independently. The assembly of EAST-NBI-2 accomplished in April 2015 after finishing the assembly of EAST-NBI-1 in 2013. The two injectors attended EAST experiment campaign of 2015 and are attending EAST...
Dr
Yohji Seki
(National Institutes for Quantum and Radiological Science and Technology)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
R&Ds for starting operation with a full- tungsten (W) ITER (INB-174) divertor have been enhanced by recommendation of the ITER council since 2011. Japan Atomic Energy Agency (JAEA) as Japanese Domestic Agency (JADA) and the ITER organization (IO) have been actively working on the development and demonstration on the full-W ITER divertor under the framework of the task agreement. JAEA is in...
Dr
Liqun Hu
(Institute of Plasma Physcis, Chinese Academy of Sciences)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Great progress has been made to the design of ITER Radial X-ray Camera (RXC). The structure design is optimized and installation process is studied considering the simplification and easiness of maintenance. Remote handling skills and tools are designed for the system maintenance after being activated. For detector cooling against high environment temperature which can be up to 240℃, a...
Dr
Ryota Imazawa
(Japan Atomic Energy Agency)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
PoPola measures both orientation angle (θ) and ellipticity angle (ε) of polarization state of multiple probing far-infrared (FIR) laser beams (wavelength is 119 μm). The change of θ and ε are mainly associated with the Faraday and the Cotton-Mouton effects, respectively, and provide information of electron density, electron temperature and magnetic field. Equilibrium reconstruction of PoPola...
Dr
Jerome Bucalossi
(CEA)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The WEST platform, which is a major evolution of Tore Supra towards a steady-state tungsten diverted tokamak, is targeted at minimizing risks for ITER divertor procurement and operation.
This paper presents an overview of the status and relevant technical issues for the new platform. At the time of the writing, the 4 meter diameter thick casing of the upper and lower divertor in-vessel coils...
Dr
Ivan Vargas-Blanco
(Costa Rica Institute of Technology)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The low aspect ratio spherical tokamak (ST) MEDUSA (Madison EDUcation Small Aspect.ratio tokamak) is currently being re-commissioned in Costa Rica and was donation to Costa Rica Institute of Tecnology by University of Wisconsin-Madison, USA. The major characteristics of this device are [1]: plasma major radius R_o < 0.14m, plasma minor radius a < 0.10m, plasma vertical elongation 1.2, toroidal...
Dr
zhiquan song
(Institute of Plasma Physics, Chinese Academy of Science,)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
This paper presents the research and development (R&D) progress of the ITER Polodial Field (PF) converter for the coil power supply system applied in the ITER project. The PF converter system is composed of 14 PF Converter Units (PFCU), with a total apparent power of 1.2 GVA and a rated dc current of 55 kA. Due to the huge system power, unprecedented short circuit level, high reliability and...
Mr
Dong Hyeon Na
(Seoul National University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
For several years, dedicated experiments have been performed in the KSTAR Ohmic L-mode plasmas to investigate the rotation reversal phenomena and it was finally observed in 2015. We found that the rotation reversal can be related to the rotation gradient change with respect to the electron density or the collisionality in the region rho ~ 0.3-0.6. In KSTAR, its possible mechanism was...
Dr
Abhay Ram
(UsMIT)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In tokamak fusion plasmas, coherent, intermittent, fluctuations in the form of blobs or filaments and incoherent fluctuations due to turbulence are routinely observed in the scrape-off layer. Radio frequency (RF) electromagnetic waves, commonly used for heating the plasma and for providing non-inductive plasma current, are excited by antenna structures placed near the wall of a tokamak. These...
Dr
Fulvio Militello
(Culham Centre for Fusion Energy)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
We review the recent MAST exhaust programme which focused on the interplay between Scrape Off Layer (SOL) profiles and filaments, and on the physics of advanced divertors. MAST experiments demonstrated that the broadening of the SOL density profiles observed at high fuelling can occur in the absence of detachment and independently from ionisation sources and that it is reduced at high Ip. At...
Ms
Flavia Bonelli
(Karlsruhe Institute of Technology)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
From both the physical and the technical point of view, the description of gas dynamics in the divertor and vacuum systems in tokamak fusion reactors poses a challenging task because of the wide range of regimes covered by the flow: from continuum and slip regimes in the plasma, to transition and free molecular flow in the sub-divertor region. Nevertheless, over the past few years, significant...
Dr
Joon-Wook Ahn
(Oak Ridge National Laboratory)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Understanding of underlying physics processes that determine non-axisymmetric divertor footprints is crucial for ITER’s long pulse operation scenario in the presence of 3-D fields, as they will cause asymmetric erosion and re-deposition of divertor material. It has been recently found that plasma response plays a key role in the formation of 3-D lobe structure and divertor footprints by the...
Dr
Hao WANG
(National Institute for Fusion Science)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Energetic particle driven geodesic acoustic mode (EGAM) and Global Alfven eigenmode (GAE) in a 3-dimensional Large Helical Device (LHD) equilibrium are investigated using MEGA code. MEGA is a hybrid simulation code for energetic particles interacting with a magnetohydrodynamic (MHD) fluid. It is found that the n=10 harmonics of the 3-dimensional LHD equilibrium bring about the coupling between...
Dr
Minwoo Kim
(Ulsan National Institute of Science Technology)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
A control of the ELM-crash is required for a stable plasma operation in a fusion reactor if the H-mode is adapted as an operation scenario. In the KSTAR H-mode plasma, a comparative study between 2D ECEI images of ELMs and MHD simulations has been performed in order to study the underlying physics of the ELM necessary for establishing an effective and robust ELM control. As a first step, the...
Dr
Yongkyoon In
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Discharges on the Korea Superconducting Tokamak Advanced Research (KSTAR) device often have suffered from minor and major disruptions by a large growth of the m/n=2/1 MHD instability. It requires 3-D measurement to decipher the underlying physics of the complicated disruption dynamics. The electron cyclotron emission imaging (ECEI) system on KSTAR is used to measure a quasi 3-D electron...
Dr
Sehoon Ko
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Steep pedestal profiles of ion temperature (Ti) and toroidal rotation (VФ) are routinely observed in neutral beam injection(NBI)-heated KSTAR H-mode plasmas[W. H. Ko et al Nucl. Fusion {\bf55} 083013 (2015)]. In this work, we report a result of detailed analysis of pedestal characteristics. By analyzing a set of data with different experimental conditions, we show that Ti and VФ pedestals are...
Mr
HyunYeong Lee
(Seoul National University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
EBW is an effective heating method to generate over dense plasma in low magnetic field devices such as ST. The direct XB MC from LFS injection may be used effectively because the LFS X-mode can be easily transmitted to right hand (RH) polarized slow X wave or mode converted to highly damping Bernstein wave. In addition, it requires no injection angle adjustment and complicated hardware...
Dr
GIANLUIGI SERIANNI
(ItRFX)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ITER tokamak requires two heating Neutral Beam Injectors (NBIs), based on the neutralisation of 40A of negative hydrogen ions accelerated to 1MeV with a pulse length of one hour. As these simultaneous parameters were never experimentally achieved, in order to optimise source operation and to assess beam properties, a specific test facility (“PRIMA”) was established in Padova, comprising...
Dr
Daniele Marocco
(ENEA C. R. Frascati, Dipartimento FSN, Frascati, Italy)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The paper describes the on-going work performed by a Consortium of European institutes on the design of the ITER Radial Neutron Camera (RNC) within a framework contract placed by Fusion For Energy (F4E), the ITER European Domestic Agency. The RNC will measure the uncollided 14 MeV and 2.5 MeV neutrons from deuterium-tritium (DT) and deuterium-deuterium (DD) fusion reactions through an array of...
Dr
Yi Tan
(Tsinghua University)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Toroidal Alfven eigenmodes (TAEs) during minor disruptions have been identified in the ohmic plasmas of the SUNIST spherical tokamak. The TAE modes are observed in the frequency range of 150 - 400 kHz. The mode structure analysis indicates the existence of both m/n=-3/-1 and -4/-1 harmonics, propagating in the electron diamagnetic direction in the laboratory frame of reference. These TAEs...
Prof.
Ambrogio Fasoli
(CRPP-EPFL)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Major upgrades to the TCV infrastructure are implemented to increase the DEMO relevance of its research. A major component is the creation of an in-vessel divertor chamber of variable closure to contribute to the qualification of alternative divertor concepts, including the demonstration of advantageous plasma exhaust performance, combining detachment with particle control, He compression and...
Prof.
Jiming Chen
(Southwestern Institute of Physics)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
China will manufacture 10% of the ITER FW panels, all in EHF type with heat load up to 4.7MW/m2. A hypervapotron (HVT) cooling channel was applied as heat sink to enhance heat transfer. Small scale mock-ups have been manufactured in China and successfully passed the thermal fatigue test at 4.7 and 5.9MW/m2 for 7500cycles and 1500 cycles, respectively. Explosion bonding is used to make...
Prof.
Abdelaziz Sid
(Batna University 1)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
In the present work, the electronic distribution function for high magnetized hot plasma, taking into account the electron ion collisions, is explicitly calculated. The basic equation in this investigation is the Fokker-Planck equation where some justified approximations for fusion and astrophysical magnetized plasmas are used.. By computing the second moment of the distribution function, we...
Dr
Jong-Gu Kwak
(National Fusion Research Institute)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The importance of neutron emission measurements and modeling at present nuclear fusion device rely on its usage for designing future reactor for shielding as well as the fact that it has the information about the plasma property. Especially a small amount of nuclear heating on SC magnet impacts heavily on safe operation of machine due to tight temperature margin of quenching.
Since the...
Dr
Ferran Albajar
(Fusion for Energy)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The EU gyrotron for the ITER Electron Cyclotron heating system has been developed in coordinated efforts from several EU institutions (organized in the EGYC European Gyrotron Consortium, TED and F4E) and under the supervision of ITER Organization Central Team. The design of the ITER gyrotron is based on the EU expertise in the series production of high power and long pulse gyrotrons for the...
Dr
Taina Kurki-Suonio
(Aalto University)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
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....
Vanni Toigo
(Consorzio RFX)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In order to achieve thermonuclear-relevant plasma parameters in ITER, the auxiliary heating systems have to provide 50 MW, out of which 33 MW by two Neutral Beam Injectors (NBI), each designed to operate at 1MV, 40 A for one hour. The unprecedented parameters and the complexity of the NBI systems have led to recognize the need of a dedicated Test Facility to carry out an international R & D...
264.
Toroidal Electromagnetic Particle-in-Cell Code with Gyro-kinetic Election and Fully-kinetic ion
Mr
Jingbo Lin
(CnUSTC)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Current drive and auxiliary heating is critical for fusion plasmas. A kinetic simulation model has been developed using gyro-kinetic electron and fully-kinetic ion by removing fast gyro motion of electrons using the Lie-transform perturbation theory. A particle-in-cell kinetic code is developed based on this model in general magnetic flux coordinate systems, which is particularly suitable for...
Dr
Nicola Bertelli
(Princeton Plasma Physics Laboratory)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
The injection of fast waves (FW) in the ion cyclotron range of frequency (ICRF) is a well-established method of heating and driving current in magnetically confined toroidal plasma and it will play an important role in the ITER experiment. Taking into account self-consistently the interaction of FW with both the minority ion population and fast-ion / neutral beam populations is a crucial...
Dr
Joydeep Ghosh
(Institute for Plasma Research)
19/10/2016, 14:00
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
It is a well-known fact that small / medium-sized tokamaks have enormously contributed in design and development of large size tokamaks such as ITER for building fusion reactors in terms of physics, engineering and diagnostics. Small / medium-sized tokamaks are very convenient to develop and test new ideas, technologies and materials, which because of the risky nature cannot be done in large...
Prof.
Hyeon Park
(NFRI)
19/10/2016, 14:00
EXW - Magnetic Confinement Experiments: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Long standing issue of full vs. partial reconnection model of the sawtooth instability is revisited in Korean Superconducting Tokamak Advanced Research (KSTAR). The measured central safety factor (q(0)) by Motional Stark Effect (MSE) is ~1.0 and this measurement alone cannot validate the sawtooth instability model definitively due to non-trivial off-set error. Study of controlled experiment of...
Dr
David Green
(Oak Ridge National Laboratory)
19/10/2016, 14:00
THW - Magnetic Confinement Theory and Modelling: Wave–plasma interactions; current drive; heating; energetic particles
Poster
Linear kinetic solvers are the workhorse tools for predicting the core plasma response to applied radio-frequency (RF) power in magnetically confined fusion devices. These codes are typically frequency-domain spectral, or a combination of spectral and finite-element that require the inversion of a large, dense, or block-dense, ill-conditioned double complex matrix. On the engineering side of...
