Japan Atomic Energy Agency, Naka Fusion Institute H モード周辺プラズマの無次元量解析 Japan Atomic Energy Agency 浦野 創 原子力機構 那珂核融合研究所.

Slides:



Advertisements
Similar presentations
Physics Basis of FIRE Next Step Burning Plasma Experiment Charles Kessel Princeton Plasma Physics Laboratory U.S.-Japan Workshop on Fusion Power Plant.
Advertisements

1/15 D. C. McDonald et al, Particle and Energy Transport in Dedicated  *,  and  * Scans in JET ELMy H-modes, IAEA - 20th Fusion Energy Conference, Vilamoura,
ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
A. Kirk, 21 st IAEA Fusion Energy Conference, Chengdu, China, October 2006 Evolution of the pedestal on MAST and the implications for ELM power loadings.
Inter-ELM Edge Profile and Ion Transport Evolution on DIII-D John-Patrick Floyd, W. M. Stacey, S. Mellard (Georgia Tech), and R. J. Groebner (General Atomics)
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
1 J-W. Ahn a H.S. Han b, H.S. Kim c, J.S. Ko b, J.H. Lee d, J.G. Bak b, C.S. Chang e, D.L. Hillis a, Y.M. Jeon b, J.G. Kwak b, J.H. Lee b, Y. S. Na c,
R Sartori - page 1 20 th IAEA Conference – Vilamoura Scaling Studies of ELMy H-modes global and pedestal confinement at high triangularity in JET R Sartori.
IAEA - FEC2004 // Vilamoura // // EX/4-5 // A. Staebler – 1 – A. Staebler, A.C.C Sips, M. Brambilla, R. Bilato, R. Dux, O. Gruber, J. Hobirk,
G Saibene - 1 Dimensionless Identity Experiments in JT-60U and JET G Saibene 1, N Oyama 2, Y Andrew 3, JG Cordey 3, E de la Luna 4, C Giroud 3, K Guenther.
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
Steady State High  N Discharges and Real-Time Control of Current Profile in JT-60U T. Suzuki 1), A. Isayama 1), Y. Sakamoto 1), S. Ide 1), T. Fujita 1),
Predictive Integrated Modeling Simulations Using a Combination of H-mode Pedestal and Core Models Glenn Bateman, Arnold H. Kritz, Thawatchai Onjun, Alexei.
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.
H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team Japan Atomic Energy Agency JT-60U Tokamak: p.
H-mode characteristics close to L-H threshold power ITPA T&C and Pedestal meeting, October 09, Princeton Yves Martin 1, M.Greenwald, A.Hubbard, J.Hughes,
Edge Localized Modes propagation and fluctuations in the JET SOL region presented by Bruno Gonçalves EURATOM/IST, Portugal.
O. Sauter Effects of plasma shaping on MHD and electron heat conductivity; impact on alpha electron heating O. Sauter for the TCV team Ecole Polytechnique.
Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.
第16回 若手科学者によるプラズマ研究会 JAEA
NSTX-U NSTX-U PAC-31 Response to Questions – Day 1 Summary of Answers Q: Maximum pulse length at 1MA, 0.75T, 1 st year parameters? –A1: Full 5 seconds.
High  p experiments in JET and access to Type II/grassy ELMs G Saibene and JET TF S1 and TF S2 contributors Special thanks to to Drs Y Kamada and N Oyama.
1 Plasma Rotation and Momentum Confinement – DB ITPA - 1 October 2007 by Peter de Vries Plasma Rotation and Momentum Confinement Studies at JET P.C. de.
Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.
A. Kirk, ITPA Pedestal meeting, GA, 30 April H-mode pedestal characteristics on MAST A.Kirk, T. O’Gorman, R. Scannell Addition of new data at low.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
ASIPP HT-7 The effect of alleviating the heat load of the first wall by impurity injection The effect of alleviating the heat load of the first wall by.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
Effect of low aspect ratio data on H-mode confinement.
JT-60U -1- Access to High  p (advanced inductive) and Reversed Shear (steady state) plasmas in JT-60U S. Ide for the JT-60 Team Japan Atomic Energy Agency.
Microscopic Eddys don’t imply gyroBohm Scaling Scan device size while keeping all other dimensionless parameters fixed Turbulence eddy size remains small.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
1 LHCD Properties with a New Lower Hybrid Wave Antenna on HT-7 Tokamak Wei Wei,Guangli Kuang,Bojiang Ding,Weici Shen and HT-7 Team Institute of Plasma.
Confinement & Transport Plan Classical theory of confinement and transport. o Diffusion equation Particle diffusion in a magnetic field.
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
Dependence of Pedestal Structure on Ip and Bt A. Diallo, R. Maingi, S. Zweben, B.P. LeBlanc, B. Stratton, J. Menard, S. Gerhardt, J. Canick, A. McClean,
20th IAEA Fusion Energy Conference, 2004 Naka Fusion Research Establishment, Japan Atomic Energy Research Institute Stationary high confinement plasmas.
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
LI et al. 1 G.Q. Li 1, X.Z. Gong 1, A.M. Garofalo 2, L.L. Lao 2, O. Meneghini 2, P.B. Snyder 2, Q.L. Ren 1, S.Y. Ding 1, W.F. Guo 1, J.P. Qian 1, B.N.
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
1 Peter de Vries – ITPA T meeting Culham – March 2010 P.C. de Vries 1,2, T.W. Versloot 1, A. Salmi 3, M-D. Hua 4, D.H. Howell 2, C. Giroud 2, V. Parail.
Scaling experiments of perturbative impurity transport in NSTX D. Stutman, M. Finkenthal Johns Hopkins University J. Menard, E. Synakowski, B. Leblanc,R.
Pedestal Characterization and Stability of Small-ELM Regimes in NSTX* A. Sontag 1, J. Canik 1, R. Maingi 1, J. Manickam 2, P. Snyder 3, R. Bell 2, S. Gerhardt.
Status of NSTX/DIII-D/MAST aspect ratio core confinement comparison studies M. Peng, for E.J. Synakowski For the ITPA Transport Physics Working Group Kyota,
Darren McDonald, TFS1 meeting, 20th April /20 Proposed JET 2006 confinement experiments D C McDonald Structure of talk: Hybrid studies ELMy H-mode,
Off-axis Current Drive and Current Profile Control in JT-60U T. Suzuki, S. Ide, T. Fujita, T. Oikawa, M. Ishikawa, G. Matsunaga, M. Takechi, M. Seki, O.
1 V.A. Soukhanovskii/IAEA-FEC/Oct Developing Physics Basis for the Radiative Snowflake Divertor at DIII-D by V.A. Soukhanovskii 1, with S.L. Allen.
NSTX APS-DPP: SD/SMKNov Abstract The transport properties of NSTX plasmas obtained during the 2008 experimental campaign have been studied and.
9-12 Sept. 2002E. BARBAT0-ENEA, TTF, Cordoba1 Electron Internal Transport barriers by LHCD and ECRH in FTU-high density plasmas E. Barbato Associazione.
Study on Plasma Startup Scenario of Helical DEMO reactor FFHR-d1
Mechanisms for losses during Edge Localised modes (ELMs)
Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.
11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",
ITERに係わる原子分子過程 Atomic and Molecular Processes in ITER SHIMADA, Michiya ITER International Team Annual Meeting of Japan Society of Plasma Science and Nuclear.
2/13 Introduction Knowledge of the influence of the hydrogen isotope on H-mode confinement is essential for accurately projecting the energy confinement.
More on Pedestal and ELMs
Physics of fusion power
N. Oyama, H. Urano, Y. Sakamoto
Joint European Research Doctoral Network in Fusion Science and Engineering Edge Pedestal Profile Characteristics of H-Mode Discharges in ASDEX Upgrade.
(EX/P1-4) Type I ELMy H-mode in hydrogen and deuterium:
New Results for Plasma and Coil Configuration Studies
CHARACTERIZATION OF ISOTOPE EFFECT ON CONFINEMENT
Continued exploration of pedestal structure and edge relaxation mechanisms at lower edge collisionality  J.W. Hughes, A. Hubbard, B. LaBombard, J. Terry,
20th IAEA Fusion Energy Conference,
Automatic Analysis of Edge Pedestal Gradient Degradation during ELMs
John Sheffield ISSE U-Tennessee April 5, 2011.
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Japan Atomic Energy Agency, Naka Fusion Institute H モード周辺プラズマの無次元量解析 Japan Atomic Energy Agency 浦野 創 原子力機構 那珂核融合研究所

Japan Atomic Energy Agency, Naka Fusion Institute H-mode is considered as the standard operation mode in ITER. 1.Steady state with the existence of ELM accompanied by pulsating expulsion of heat and particle. 2.Favorable confinement due to edge transport barrier Pedestal characteristics can strongly be linked to 1.Boundary condition determining the core energy confinement 2.Characterization of ELM losses Introduction width

Japan Atomic Energy Agency, Naka Fusion Institute Dimensionless analysis on spatial width of H-mode pedestal Optimizing pedestal width  ped and height is a crucial issue to control the overall H-mode confinement. Dimensionless analysis is urgent issue for extrapolation to ITER. This is because a strong co-linearity between  and  is hard to separate out at the plasma edge.  ped expressed by non-dimensional parameters are not consistent among several devices.      F( , q, , , , …) =  ped  Examine the scaling of pedestal width by conducting the non-dimensional transport experiment introducing hydrogen discharges.

Japan Atomic Energy Agency, Naka Fusion Institute Co-linearity between  and  at the plasma edge in the H-modes Dependence of p ped on I p yields  and  * as a function of I p at * = const. This co-linearity is hard to separate in the H-mode plasmas only with a single species. ITn  I p Tn 

Japan Atomic Energy Agency, Naka Fusion Institute JT-60U Tokamak: p. 5 Examine dependence on  introducing hydrogen plasmas CONDITION: IP~1MA, BT~2, DELTA~0.3 Examine the dependence of  ped on  or  while keeping total  pol fixed in hydrogen and deuterium H-modes. (1) If  PED  , spatial profiles would deviate by m 0.5. (2) If  PED  , spatial profiles would be similar. Similar profiles are obtained in H/D plasmas. This result implies  * dependence is weak. (H. Urano, et al., NF 48 (2008) )

Japan Atomic Energy Agency, Naka Fusion Institute Power scan of satisfying  = const. in H/D plasmas reveals the  (  m 0.5 ) dependence of  ped at fixed density. Experiments on  dependence of  ped I p = 1.08 MA, B T = 2.4T  = 0.35 Power required to sustain the same  in H-plasma is ~2 times larger than that in D-plasma. Higher ELM frequency is observed in H-plasma.

Japan Atomic Energy Agency, Naka Fusion Institute Similar profiles of n e, T e, T i were obtained in H/D plasmas. Thus, mass effect clearly appeared in the  profiles (  m 0.5 ) while the profiles of  and  were similar. *

Japan Atomic Energy Agency, Naka Fusion Institute Despite of different  at the pedestal by mass ratio (~ 1.4), the similar edge profile are obtained in H/D plasmas. In a series of experiments, change of  ped is small in the variation of  pol  at fixed  pol (  ped  a p  0.2 ).  = 0.2

Japan Atomic Energy Agency, Naka Fusion Institute Experiments on  pol dependence of  ped Power scan of satisfying  pol  I p 4 at the pedestal with controlling n  I p 4 gives the variation of  pol at fixed  pol . Compare profiles at time slices when  pol * remains constant at the pedestal.

Japan Atomic Energy Agency, Naka Fusion Institute In the peripheral region,  is varied while keeping  and  fixed. *

Japan Atomic Energy Agency, Naka Fusion Institute When  (  T 0.5 /I p ) remains constant at the pedestal,  ped becomes wider at higher  pol plasma. Appropriate power scan gives a data set with the variation of . Then, the relation of  ped  a p  0.5 is obtained  pol  ped /a p  = 0.5

Japan Atomic Energy Agency, Naka Fusion Institute Scaling of pedestal width  pol  0.2  pol 0.5  ped / a p D H Based on the non-dimensional transport experiments using H/D plasmas, the scaling on H-mode pedestal width is obtained Rho dependence of the pedestal width is weak while it depends strongly on beta.  ped  a p  0.2  0.5  ped  a p 

Japan Atomic Energy Agency, Naka Fusion Institute Summary Conducting the H-mode experiments using hydrogen (H) and deuterium (D) discharges, dependence of pedestal width on non-dimensional parameters were examined. Similar pedestal profiles were obtained at H/D plasmas. When  is raised, pedestal width increased with a relation expressed as  ped  a p  0.2  0.5.