Mr
Gunyoung Park
(Korea, Republic of)
17/10/2014, 14:00
Poster
High confinement mode (H-mode) is essential as a baseline operating scenario in ITER. In order to develop a predictive model of the power threshold for access to H-mode in ITER, it is essential to understand first the underlying mechanism that triggers the transition. It is widely accepted that edge transport barrier (ETB) formation in H-mode is due to the suppression of turbulence by E x B...
Prof.
Hyeon K. Park
(UNIST)
17/10/2014, 14:00
Poster
An accurate method to estimate the tearing mode stability parameters, i.e. the classical stability index (Δ') and the critical width for pressure flattening (w_c), has been developed based on electron cyclotron emission imaging (ECEI) diagnostic in the KSTAR. The measured ECE images of tearing modes are compared with synthetic images reconstructed from the tearing mode T_e model for the...
Dr
Victor Bykov
(Germany)
17/10/2014, 14:00
Poster
The Wendelstein 7-X (W7-X) optimized stellarator is presently under final stage of assembly at the Max-Planck-Institut für Plasmaphysik in Greifswald. The goal of W7-X is to verify that the advanced stellarator magnetic confinement concept is a viable option for a fusion reactor.
The coil system consisting of 70 superconducting coils of seven different types is supported by a massive central...
Mr
Egemen Kolemen
(USA)
17/10/2014, 14:00
Poster
Novel control schemes have been implemented at DIII-D to test and optimize heat-handling capabilities and burn regulation for advanced tokamaks. The topological instability of the snowflake (SF) configuration, which has a second-order null-point, motivated implementation of a control system to sustain the SF. We implemented the world’s first real-time SF detection and control system on DIII-D...
Dr
Won-Ha Ko
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
This paper describes the change of the rotation profiles driven by the sawtooth crashes and its effect on the LH trasition in KSTAR. After sawtooth crashes, the basic features of a slowly rising central electron temperature(Te) followed by a rapid drop in temperature have been frequently observed on many tokamaks and the rise of the central toroidal rotation and ion temperature (Ti) have been...
Dr
Tsuyoshi Akiyama
(National Institute for Fusion Science)
17/10/2014, 14:00
Poster
This paper describes a conceptual design of the density measurement system on the helical reactor FFHR-d1 based on its quantitative operation scenario.
One of the important plasma parameters which is used for plasma control is the line averaged electron density on FFHR-d1. This is because the startup and the steady state plasma will be mainly operated by feedback control of the line averaged...
284.
Coupling between Intrinsic Rotation and Turbulence-Driven Residual Stress in the TEXTOR Tokamak
Prof.
Yuhong Xu
(Southwestern Institute of Physics)
17/10/2014, 14:00
Poster
Direct measurements of residual stress (force) have been executed at the edge of the TEXTOR tokamak using multi-tip Langmuir and Mach probes, together with counter-current NBI torque to balance the existing toroidal rotation. Substantial residual stress and force have been observed at the plasma boundary, confirming the existence of a finite residual stress as possible mechanisms to drive the...
Prof.
Kaiming Feng
(Southwestern Institute of Physics)
17/10/2014, 14:00
Poster
China had promised to test its TBM modules during different ITER operation phase and have signed the CN HCCB TBMA with ITER IO recently. Related design and R&D activities for each TBM modules with auxiliary systems and interface with ITER facility were introduced. The preliminary conceptual design of CN HCCB TBM has been completed while the design optimization is in progress. Basic...
Dr
Vladimir Vershkov
(ITF NCR "Kurchatov Institute")
17/10/2014, 14:00
Poster
The paper presents new insight into previous and new experimental data of the turbulent density fluctuations behavior in T-10 OH and ECRH discharges. The experiments showed existence of the same maximal peaked pressure profile in both OH and ECRH tokamak plasmas as well as strong deterioration of particle confinement after plasma reach this profile (fast density decay in OH, “density pump out”...
Dr
Nagato Yanagi
(National Institute for Fusion Science)
17/10/2014, 14:00
Poster
Conceptual design studies of the LHD-type helical fusion reactor, FFHR-d1, are progressing steadfastly. The magnet system consists of a pair of helical coils (major radius 15.6 m) and two pairs of vertical field coils. A 3 GW fusion power generation requires a toroidal magnetic field of 4.7 T and the total stored magnetic energy reaches 160 GJ. A conductor current of 94 kA is needed at the...
Dr
Max Salvador
(Universidad Autonoma de Nuevo León)
17/10/2014, 14:00
Poster
The Fusion Research Group (GIF, Spanish acronyms) of the Autonomous University of Nuevo Leon (UANL, Spanish acronyms) presents its advances into the toroidal coil testing bench system, toward the reinforcement of the Tokamak Experimental Facility. This tokamak design has been beneficiated from the Mexican Public Education Secretary (UANL-EXB-156), is a D-shaped Tokamak with the next main...
Mr
Anthony W. Leonard
(USA)
17/10/2014, 14:00
Poster
Recent DIII-D results using the snowflake (SF) divertor configuration demonstrate that the SF geometry enables significant manipulation of divertor heat transport for power spreading in attached and radiative divertor regimes, between and during edge localized modes (ELMs), while maintaining good H-mode confinement. Enhanced heat transport through the low poloidal field null-point region and...
Dr
Masahiko Emoto
(National Institute for Fusion Science)
17/10/2014, 14:00
Poster
The enhanced-interlink system of experiment data and numerical simulation has been developed, and successfully operated routinely in LHD. This system consists of analyzed diagnostic data, real-time coordinate mapping, and I/O to numerical simulation. It has enabled automated data handling/transferring between experiment and numerical simulation, to extensively perform experiment analyses. It...
Prof.
Yousuke Nakashima
(Plasma Research Center, University of Tsukuba)
17/10/2014, 14:00
Poster
This paper presents the first achievement of detachment from high temperature plasma equivalent to the SOL plasma of tokamaks using a large tandem mirror device. In Plasma Research Center, University of Tsukuba, we have started divertor simulation experiments at the end-cell of GAMMA 10/PDX (E-divertor) in order to realize the divertor simulation closely resemble to actual divertor environment...
Dr
Yongjin Feng
(Southwestern Institute of Physics)
17/10/2014, 14:00
Poster
For the Chinese Helium Cooled Ceramic Breeder Test Blanket Module (CN HCCB TBM) design, the tritium breeder and the neutron multiplier are considered as two important functional materials to increase the tritium breeding ratio (TBR) performance. Lithium Orthosilicate is selected as reference tritium breeder material, and Beryllium is selected as neutron multiplier in the design. The main line...
Dr
Jayhyun Kim
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
During 2013 KSTAR campaign, we conducted mixed non-axisymmetric (NA) field experiments to investigate the effect of overlap between differently aligned NA fields by the field error correction coils. Locking and error field (EF) penetration were induced by the torque imbalance between the intrinsic rotation and external magnetic braking. Further increase of the n=1 EF resulted in minor...
Mr
Alexey Sushkov
(NRC Kurchatov Institute)
17/10/2014, 14:00
Poster
The project of the T-15 tokamak modernization is now starting to be implemented at the Kurchatov Institute. The main objectives of the research program of the modernized T-15 are: steady-state operation; real time plasma current and pressure control in order to increase ßN (Advanced Tokamak operation); analysis of Te/Ti effect on the confinement properties; studies of the effects of Zonal flows...
Dr
Simon McIntosh
(Culham Centre for Fusion Energy)
17/10/2014, 14:00
Poster
The term “double decker divertor” refers to a novel divertor concept in which the inboard leg of a single null poloidal field divertor is pulled around the interior of the vacuum vessel to allow it to be treated as an outboard leg. This topology reduces the inboard leg parallel heat flux by increasing the target radius, moving the plasma wall interaction to an area of lower magnetic field....
Dr
Lorenzo Virgilio Boccaccini
(Karlsruhe Institute of Technology)
17/10/2014, 14:00
Poster
The EU Fusion Roadmap foresees the development and construction of a DEMO reactor that will deliver several 100s of MW of net electrical power starting from 2050. Although the EU breeding blanket programme has a long history of more than 30 years, this ambitious goal presents a significant challenge. The breeding blanket however will require a significant development R&D to cope with the...
Prof.
Zengyu Xu
(Southwestern Institute of Physics)
17/10/2014, 14:00
Poster
MHD geometry sensibility phenomenon was accidentally measured while an experimental investigation of MHD effect was conducting of the flow channel inserts (FCI) for liquid metal (LM) blanket system. Though the geometry sensibility phenomenon (or called secondary flow MHD effect) is successfully used to understand FCI duct flow behaviors, but, up to now, it is very little about secondary flow...
Mr
Francisco Hernandez Gonzalez
(Karlsruhe Institute of Technology)
17/10/2014, 14:00
Poster
PREMUX is a key experiment in the roadmap for a full-scale test of a Helium Cooled Pebble Bed Breeder Unit (HCPB BU) mock-up at the Karlsruhe Institute of Technology in Germany. This experiment reproduces a slice of the BU corresponding to the most thermally loaded region of the Li4SiO4 pebble bed in the BU.
The experiment has 3 main goals: (1) to serve as a test rig to validate the...
Dr
Hyungho LEE
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
Although tokamaks confine plasmas with an axisymmetric toroidal magnetic field, there is always a slight non-axisymmetric magnetic perturbations (NAMPs) resulted from the misalignment of the toroidal magnetic field coils or ripple error fields due to the finite number of toroidal magnetic field coils. NAMPs can also appear due to MHD activities (internal kink modes, tearing modes, etc.) or...
Mr
Ulrich Stroth
(Germany)
17/10/2014, 14:00
Poster
Turbulent transport remains one of the most important and challenging topics in fusion research. Scientific understanding of the related physical processes can only be enhanced through a close comparison of numerical simulations with experimental data. Microwave-based diagnostics represent almost the sole experimental approach capable of capturing plasma parameter fluctuations with the...
Dr
Tamara Andreeva
(Max-Planck-Institut für Plasmaphysik, Teilinstitut Greifswald, Germany)
17/10/2014, 14:00
Poster
Wendelstein 7-X, currently under construction at the Max-Planck-Institut für Plasmaphysik in Greifswald, Germany, is a continuation of the helical advanced stellarator line, with the final goal to demonstrate the reactor capability of modular stellarators. The magnet system of the machine consists of 50 non-planar and 20 planar coils, which are arranged in five identical modules.
If the...
Mr
Lothar Schmitz
(USA)
17/10/2014, 14:00
Poster
Developing a physics-based model of the L-H transition is critical for confidently extrapolating the auxiliary heating requirements for ITER from the existing empirical L-H transition power threshold scaling. For the first time, it is shown here that the initial turbulence collapse preceding the L-H transition is caused by turbulence-generated (positive) E×B flow opposing the equilibrium...
Dr
Vladimir Minaev
(Ioffe Institute)
17/10/2014, 14:00
Poster
The Globus-M spherical tokamak has demonstrated practically all of the project objectives. The main factor, limiting further enhancement of plasma parameters, is the relatively low toroidal magnetic field. The increasing of the magnetic field up to 1.0 T together with the plasma current up to 0.5 MA will entail serious rise in loads on the magnetic system in the upgraded tokamak Globus-M2....
Prof.
Hyeon K. Park
(Korea, Republic of)
17/10/2014, 14:00
Poster
A variety of helical structures such as dual or multiple flux tubes, distinct from the normal m=1 internal kink, are commonly observed in sawtoothing plasmas in the KSTAR tokamak assisted by electron cyclotron heating (ECH). Detailed 2D and quasi-3D images have shown that the dual flux tubes have m/n=1/1 helicity, co-rotate around the magnetic axis, and later merge into a single m=1 mode prior...
Arturs Zarins
(University of Latvia, Institute of Chemical Physics, Riga, Latvia)
17/10/2014, 14:00
Poster
In ITER (International Thermonuclear Experimental Reactor) several concepts of Test Blanket Modules (TBMs) will be tested and verified, because the tritium breeding is a key issue in future burning plasma machines, like, DEMO. The Helium Cooled Pebble Bed (HCPB) TBM, proposed by the European Union, will use lithium orthosilicate pebbles with 2.5 wt% excess of silica as reference tritium...
Dr
Sang-hee Hahn
(Korea, Republic of)
17/10/2014, 14:00
Poster
The realization of a wide variety of plasma shapes with varying plasma current density profiles places challenging demands on the vertical control system. In particular the bootstrap current scales quadratically with elongation at fixed normalized β_N = β_TaB_T/I_p where I_p is the plasma current, B_T is the toroidal field, and β_T = P/(B_T^2/2μ_0) and P is the volume averaged plasma...
Mr
Christopher Lowry
(European Commission)
17/10/2014, 14:00
Poster
Power exhaust is recognised to be one of the major challenges to achieving power generation by magnetically confined thermonuclear fusion. In order to reduce the power density conducted to the divertor targets to a level that can be tolerated by available technologies it will be necessary to radiate close to 100% of the exhaust power. Although it is foreseen that a significant fraction of this...
Dr
Suk-Ho Hong
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
We present the in-vessel dust velocity distribution and its correlation with toroidal rotation of plasma. Main diagnostic for the dust monitoring is visible CCD cameras and toroidal rotation of plasma is measured by charge exchange spectroscopy (CES).
4129 dust trajectories (1237 dusts in 2010 campaign, 1821 dusts in 2011 campaign, 1071 dusts in 2012 campaign) were analyzed. The dust velocity...
Prof.
Yong-Su Na
(Seoul National University)
17/10/2014, 14:00
Poster
A reversal of the intrinsic toroidal rotation at the core region has been observed in Ohmic plasmas of various tokamaks as confinement characteristics changes from the low density linear Ohmic confinement (LOC) regime to the saturated Ohmic confinement (SOC) regime. On the other hand, dedicated experiments on KSTAR in search of this phenomenon have not exhibited any toroidal rotation reversal...
Dr
Yutaka Kamada
(Japan Atomic Energy Agency)
17/10/2014, 14:00
Poster
The most distinctive feature of the superconducting magnet system for JT-60SA is the optimized coil structure in terms of the space utilization as well as the highly accurate coil manufacturing as follows, thus meeting the requirements for the steady-state tokamak research: A conceptually new outer inter-coil structure is introduced to the toroidal field coils to realize their slender shape,...
Dr
Sang-hee Hahn
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
Recent understanding of the L-H transition phenomena developed a possible explanation that a gas-induced density profile change can trigger a “Stimulated edge transport barrier (ETB)” state, which can be used to reduce the required power threshold relative to the known power threshold scalings for standard fueling.
Experimental investigations on these stimulated transitions were carried in...
Mr
YoungHwa An
(Seoul National University)
17/10/2014, 14:00
Poster
The effect of the poloidal field structure on pre-ionization and start-up has been investigated with a special focus on the trapped particle configuration in VEST (Versatile Experiment Spherical Torus), a spherical torus recently built at Seoul National University. VEST is characterized by two partial solenoid coils installed at both vertical ends of a center stack, which is intended to be...
Dr
Richard Martin
(CCFE)
17/10/2014, 14:00
Poster
The Mega Amp Spherical Tokamak (MAST) is a centre piece of the UK fusion research programme. A MAST Upgrade programme is under way with three primary objectives: 1) To develop reactor-relevant advanced divertor concepts, in particular long leg and Super-X configurations; 2) Add to the knowledge base for ITER, by addressing important plasma physics questions and developing predictive models...
Dr
Woochang Lee
(POSTECH)
17/10/2014, 14:00
Poster
Mean apparent poloidal rotations of ion-scale density fluctuations in the laboratory frame were observed with the microwave imaging reflectometer (MIR) system in KSTAR ohmic and neutral beam (NB) heated L-mode plasmas. The estimated apparent poloidal velocities are 1-2 km/s at r/a ~ 0.5 in the electron diamagnetic direction for ohmic plasmas, and 8-10 km/s at r/a ~ 0.6 and 5-6 km/s at r/a ~...
Mr
Jiaqi Dong
(China)
17/10/2014, 14:00
Poster
Understanding the physics mechanism of low-high (L-H) confinement transitions in toroidal plasmas is essential for ensuring heating power requirements for future fusion reactors. Early experiments show that plasma may enter an intermediate phase (I-phase) with limit cycle oscillations (LCOs) of plasma parameters and pass through a slow L-H transition if heating power is close to the H-mode...
Dr
Ernest Platacis
(Institute of Physic of University of Latvia (IPUL))
17/10/2014, 14:00
Poster
The report describes and presents for the potential collaborators the MHD PbLi experimental facility at IPUL designed for liquid metal blanket related investigations. As the key element of the facility the cryogen-free magnet systems should be considered providing an up to 5T field in a D=30 cm and L=100 cm bore. Since a water cooled heat shielding is installed working temperatures up to...
Mr
Baurzhan Chektybayev
(Institute of Atomic Energy of National Nuclear Center of Republic Kazakhstan)
17/10/2014, 14:00
Poster
In the paper is described new endoscopic visualization system of KTM tokamak which allows to observe plasma through the long equatorial port. System has been designed to observe processes inside plasma and the processes due to plasma-wall interactions.
Design of KTM's visualization system based on special image fiber bundle and entrance wide angle objective lens, which allows to have image of...
Dr
Marina Becoulet
(IRFM/CEA)
17/10/2014, 14:00
Poster
The intensive experimental and theoretical study of Edge Localized Modes (ELMs) and methods for their control has a great importance for ITER. The application of small external Resonant Magnetic Perturbations (RMPs) has been demonstrated to be efficient in ELM suppression/mitigation in present day tokamaks. RMPs are foreseen as one of the promising methods of ELM control in ITER. In the...
Dr
Guido Huijsmans
(ITER Organization)
17/10/2014, 14:00
Poster
Validation of MHD models and MHD simulations on current experiments is needed to provide a physics basis for the application of these models to ITER. This paper describes the progress made towards validation in the area of the stability of the H-mode edge pedestal and ELM control.
ELM control: pellet pacing
The injection of pellets is one of the methods foreseen to control ELM energy losses...
Prof.
Yong-Su Na
(Seoul National University)
17/10/2014, 14:00
Poster
The ohmic breakdown is the one of major methods to initiate the plasma in various devices. The electron avalanche, the main mechanism of the ohmic breakdown, is well described by traditional Townsend avalanche theory in the case of low pressure gas and simple slab geometry. The physical mechanism of the ohmic breakdown process in the tokamak, however, is not fully understood yet due to...
Mr
Arne Kallenbach
(Germany)
17/10/2014, 14:00
Poster
To ensure a sufficient divertor lifetime ITER and a future DEMO reactor will operate under at least partial detachment (PD). PD is defined as a significant reduction of heat flux and pressure along field lines between mid-plane and divertor target for the first few power decay lengths in the scrape-off layer. For PD conditions in ASDEX Upgrade (AUG) the peak heatflux in the divertor is below 5...
Dr
Hyunyong Lee
(Korea Advanced Institute of Science and Technology)
17/10/2014, 14:00
Poster
This paper describes the pedestal characteristics during the Edge Localized Mode (ELM) mitigation by Super-sonic Molecular Beam Injection (SMBI) on KSTAR. After SMBI, whose pressure and duration time are 1 MPa and 8 ms, respectively, the reductions in both amplitude and time interval of D_alpha signals indicate the mitigation of type I-like ELM by SMBI. Despite the cold neutral gas injected by...
Linda Sugiyama
(M.I.T.)
17/10/2014, 14:00
Poster
The Ignitor Program maintains the objective of approaching D-T ignition conditions by incorporating systematically advances in high magnetic field technology and in experiments on high density well confined plasmas. Another objective is to chart the development of the high field line of experiments. Considering that a detailed machine design has been carried out [1], a subset of the areas to...
Mr
Nobuyuki Asakura
(Japan)
17/10/2014, 14:00
Poster
Magnetic configurations of advanced divertor, i.e. super-X (SXD) and snowflake, were recently proposed, and the concepts have been demonstrated in experiments. For the application to the Demo reactor, engineering design as well as the plasma performance should be determined. A short super-X divertor (short-SXD) is proposed as a new option for Demo divertor, where field line length from the...
Dr
Young-Seok Park
(Columbia University)
17/10/2014, 14:00
Poster
H-mode plasma operation of KSTAR has been expanded to reach the ideal MHD no-wall beta limit. The closest approach to this limit has achieved high normalized beta, beta_N, up to 2.8 while reducing plasma internal inductance, l_i, to near 0.7 exceeding the computed n = 1 ideal no-wall limit. The ratio of beta_N/l_i, has reached 4 and the maximum plasma stored energy has exceeded 0.5 MJ. As a...
Prof.
Sergei Krasheninnikov
(University California San Diego)
17/10/2014, 14:00
Poster
The processes involving plasma-material interactions in magnetic fusion devices are very multifaceted and include a wide spectrum of phenomena ranging from plasma recycling and transport of hydrogen species in the wall material to the modification of wall properties, surface morphology, and dust formation which, being ejected from the wall, can have crucial impact on plasma performance. Here...
Prof.
Hong Bing Xu
(Southwest Institute of Physics)
17/10/2014, 14:00
Poster
A DC glow discharge system is in preparation for ITER with primary aim to control impurities and particle recycling. On the current design stage, GDC electrode will be integrated into a Diagnostic Port Plug (DPP) as a part of the assembly. A Gap structure is used as electrical insulation among GDC electrode, DFW and DSM. Whiletime, in order to avoid glow discharge generated by the cooling...
Dr
Patrick Decool
(CEA, IRFM, F-13108 St-Paul-lez-Durance, France)
17/10/2014, 14:00
Poster
In 2005, when the ITER site decision was made, the French Government decided to participate to the joint Europe-Japan implementation of the so-call “Broader Approach Activities” (BA) in support of the ITER project and DEMO activities. The BA comprises the ITER Satellite Tokamak Programme (STP) which consists in upgrading the JT-60U machine into the largest fully superconducting and actively...
Mr
Hiroshi Kasahara
(Japan)
17/10/2014, 14:00
Poster
An ultra-long-pulse plasma with a duration time of 48 min, a line-averaged electron density of 1.2x10^19 m^-3, and electron and ion temperatures (Te, Ti) of 2 keV has been achieved by the averaged heating power (P_ECH+ICH) of 1.2 MW for helium plasma. The heating energy injected into plasma reached 3.36 GJ, which is a new world record in toroidal plasmas. Three types of ICRF antennas were...
Dr
Steven Sabbagh
(Columbia University)
17/10/2014, 14:00
Poster
The National Spherical Torus Experiment - Upgrade (NSTX-U) is the most powerful spherical torus facility being constructed at PPPL, Princeton USA. The NSTX-U project has entered the last phase of construction, and preparation for plasma operations is now underway. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based...
Dr
Elena Gaio
(Consorzio RFX)
17/10/2014, 14:00
Poster
JT-60SA satellite tokamak is an experimental device, presently under construction, equipped with superconducting Toroidal Field (TF) and Poloidal Field (PF) magnets, capable of confining high temperature plasmas (current up to 5.5 MA) for 100 s [1]. The majority of the new power supplies are provided by Europe, and the Italian National Research Council (CNR), acting through Consorzio RFX,...
Mr
Pinghuai Wang
(Southwestern Institute of Physics, Chengdu, Sichuan, China)
17/10/2014, 14:00
Poster
To provide structural material support for the design and fabrication of Chinese Helium-Cooled Ceramic tritium Breeder test blanket module (CN HCCB TBM) as well as for China demonstration (DEMO), a kind of Reduced Activation Ferritic/Martensitic (RAFM) steel named CLF-1 has been developed at Southwestern Institute of Physics (SWIP) in China since 2003.
With the cooperation among domestic...
Ms
Irina Tazhibayeva
(Institute of Atomic Energy, National Nuclear Center RK)
17/10/2014, 14:00
Poster
Research program of the lithium divertor module at tokamak KTM includes the following tasks: study of lithium behavior under tokamak’s condition and lithium influence on vacuum conditions; study of the processes of plasma interaction with lithium surface; study of lithium influence on plasma parameters; and study of the shielding effects of receiving divertor surface due to re-emitting on...
Dr
Stylianos Varoutis
(Karlsruhe Institute of Technology)
17/10/2014, 14:00
Poster
Over the last few years much effort has been invested in modeling the complex geometry of divertor and subdivertor region in tokamak fusion reactors. The main goal is the investigation of the impact of neutral gas dynamics on the particle removal process, during operation. Depending on the plasma conditions, the neutral gas flow starts from viscous regime above the dome and close to divertor...
Mr
Hyeon Keo Park
(Korea, Republic of)
17/10/2014, 14:00
Poster
Following successful characterization of the growth, saturation and bursting process of the Edge Localized Mode (ELM) by a 2D/3D Electron Cyclotron Emission Imaging (ECEI) system in KSTAR H-mode plasmas, the observed mode structure is verified via synthetic image reconstruction based on the BOUT++ code. In successive KSTAR campaigns, a wide range of toroidal mode numbers (~4 < n < ~~6) of the...
Mr
Englen Azizov
(Russian Federation)
17/10/2014, 14:00
Poster
Status of T-15 upgrade tokamak is presented. T-15 upgrade tokamak has the following parameters: R=1.48 m, a=0.67 m, B=2.0 T, Ipl= 2.0 MA. Poloidal system is capable of realizing the divertor both with single null and double null magnetic configuration and plasma shape with elongation k95 = 1.7-1.9 and triangularity delta 0.3-0.4. Installation will equipped with the auxiliary plasma heating and...
Dr
Kazuo Hoshino
(Japan Atomic Energy Agency)
17/10/2014, 14:00
Poster
The power handling in the divertor is one of the most crucial issues for a fusion reactor design. In the previous study of development of the power handling scenario for a compact DEMO reactor, SlimCS, further reduction of the target heat load was required even in the case where more than 90% of the exhausted power from the core plasma was radiated by the argon impurity gas seeding. In this...
Dr
JaeChun Seol
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
In this paper, we report the characteristics of Type III ELM in KSTAR mostly focusing on the Type III ELM regime after L-H transition. In the KSTAR tokamak, Type III ELMs are frequently observed after the transition from L-mode to H-mode. The repetition frequency of the Type III ELMs is 200~1000 Hz. As the edge plasma pressure increases, ELM-free regime occurs, which is followed by Type I ELM...
Dr
Pierluigi Bruzzone
(EPFL-CRPP)
17/10/2014, 14:00
Poster
After completing the qualification tests of the ITER cable-in-conduit conductors (CICC), the series manufacture tests are running in the SULTAN test facility in Villigen, Switzerland, with target completion date in 2015. The key test for the conductor samples is the current sharing temperature, Tcs, at the nominal operating field and current, i.e. the maximum temperature at which the...
Mr
Alexandr Novokhatsky
(Ioffe Physical-Technical Institute of the Russian Academy of Sciences)
17/10/2014, 14:00
Poster
Current research is the first investigation of cyclic plasma-wall interaction with tungsten elements designed for ITER divertor on Globus-M tokamak. The experiment is focusing on surface morphology, chemical composition and structure of pre-melted (damaged) layers of tungsten after irradiation by electron beam and plasma jet. The irradiated by the electron beam and plasma jet ITER - like...
Mr
Derek Sutherland
(University of Washington)
17/10/2014, 14:00
Poster
A high-β spheromak reactor concept called the dynomak has been designed with an overnight capital cost that is competitive with conventional power sources. This reactor concept utilizes recently discovered imposed-dynamo current drive (IDCD) and a molten salt (FLiBe) blanket system for first wall cooling, neutron moderation and tritium breeding. Currently available materials and ITER developed...
Mr
Andreas Dinklage
(Germany)
17/10/2014, 14:00
Poster
The stellarator concept offers a possible alternative to a tokamak Fusion Power Plant (FPP). One of the missions of the EU Roadmap to the realisation of fusion energy is to develop the stellarator line to maturity. World-wide efforts on different stellarator lines cover a substantial range of candidate magnetic configurations; the EU programme focuses on the optimized, helical advanced...
Dr
Alexey Gurchenko
(Ioffe Institute)
17/10/2014, 14:00
Poster
The interaction between large-scale mean E×B flows, geodesic acoustic modes (GAM) and small-scale drift-wave turbulence has been an important area of experimental research for anomalous transport of energy and particles in toroidal plasmas during the last decade utilizing more and more sophisticated tools.
In this paper results of investigation of the interplay of GAMs and broadband drift...
Mr
Katsuji ICHIGUCHI
(Japan)
17/10/2014, 14:00
Poster
In the recent study of magnetically confined fusion plasmas, resonant magnetic perturbations (RMPs) are studied from the viewpoint of the magnetohydrodynamics (MHD) stability against pressure driven modes, because RMPs can locally change the pressure gradient. Particularly, in heliotrons, since pressure driven modes are the most dangerous, the change of the pressure gradient can directly...
Dr
Sang Gon Lee
(National Fusion Research Institute)
17/10/2014, 14:00
Poster
An investigation of toroidal rotation and momentum transport was carried out at KSTAR. The impurity toroidal rotation has been observed in the core region from the Doppler shift of helium-like argon x-ray line with various plasma discharges including a pure ohmic heating and neutral beam injection (NBI). In the ohmic plasmas, the direction and magnitude of the core rotation strongly depends on...
