1 Integrated Simulation Code for Burning Plasma Analysis T.Ozeki, N.Aiba, N.Hayashi, T.Takizuka, M.Sugihara 2, N.Oyama JAERI 、 ITER-IT 2 IEA Large Tokamak.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
Cyclic MHD Instabilities Hartmut Zohm MPI für Plasmaphysik, EURATOM Association Seminar talk at the ‚Advanced Course‘ of EU PhD Network, Garching, September.
Introduction to Spherical Tokamak
Discussion on application of current hole towards reactor T.Ozeki (JAERI) Current hole plasmas were observed in the large tokamaks of JT-60U and JET. This.
Integrated Effects of Disruptions and ELMs on Divertor and Nearby Components Valeryi Sizyuk Ahmed Hassanein School of Nuclear Engineering Center for Materials.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
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),
Simple Core-SOL-Divertor Model To Investigate Plasma Operation Space Joint Meeting of US-Japan JIFT Workshop on Theory-Based Modeling and Integrated Simulation.
Modeling of ELM Dynamics for ITER A.Y. PANKIN 1, G. BATEMAN 1, D.P. BRENNAN 2, A.H. KRITZ 1, S. KRUGER 3, P.B. SNYDER 4, and the NIMROD team 1 Lehigh University,
T. Hellsten IEA Burning Plasma Workshop, July 2005 Tarragona Spain Integrated Modelling of ICRH and AE Dynamics T. Hellsten, T. Bergkvist, T. Johnson and.
Predictive Integrated Modeling Simulations Using a Combination of H-mode Pedestal and Core Models Glenn Bateman, Arnold H. Kritz, Thawatchai Onjun, Alexei.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
6 th Japan-Korea Workshop on Theory and Simulation of Magnetic Fusion Plasmas Hyunsun Han, G. Park, Sumin Yi, and J.Y. Kim 3D MHD SIMULATIONS.
TOTAL Simulation of ITER Plasmas Kozo YAMAZAKI Nagoya Univ., Chikusa-ku, Nagoya , Japan 1.
JT-60U Resistive Wall Mode (RWM) Study on JT-60U Go Matsunaga 松永 剛 Japan Atomic Energy Agency, Naka, Japan JSPS-CAS Core University Program 2008 in ASIPP.
Calculations of Gyrokinetic Microturbulence and Transport for NSTX and C-MOD H-modes Martha Redi Princeton Plasma Physics Laboratory Transport Task Force.
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
Japanese Efforts on the Integrated Modeling - Part II : JAEA Contribution - T. Takizuka (JAEA) acknowledgments : T. Ozeki, N. Hayashi, N. Aiba, K. Shimizu,
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
Integrated Modeling and Simulations of ITER Burning Plasma Scenarios C. E. Kessel, R. V. Budny, K. Indireshkumar, D. Meade Princeton Plasma Physics Laboratory.
1 Development of integrated SOL/Divertor code and simulation study in JT-60U/JT-60SA tokamaks H. Kawashima, K. Shimizu, T. Takizuka Japan Atomic Energy.
Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.
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.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
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.
G.Huysmansworkshop : Principles of MHD 21-24/3/2005 MHD in Tokamak Plasmas Guido Huysmans Association Euratom/CEA Cadarache, France with contributions.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
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.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
Integrated Modeling for Burning Plasmas Workshop (W60) on “Burning Plasma Physics and Simulation 4-5 July 2005, University Campus, Tarragona, Spain Under.
Plasma-wall interactions during high density operation in LHD
(National Institute for Fusion Science, Japan)
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
SLM 2/29/2000 WAH 13 Mar NBI Driven Neoclassical Effects W. A. Houlberg ORNL K.C. Shaing, J.D. Callen U. Wis-Madison NSTX Meeting 25 March 2002.
Edge-SOL Plasma Transport Simulation for the KSTAR
Kinetic MHD Simulation in Tokamaks H. Naitou, J.-N. Leboeuf †, H. Nagahara, T. Kobayashi, M. Yagi ‡, T. Matsumoto*, S. Tokuda* Joint Meeting of US-Japan.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
QAS Design of the DEMO Reactor
Physics Analysis and Flexibility Issues for FIRE NSO PAC-2 Meeting January 17-18, 2001 S. C. Jardin with input from C.Kessel, J.Mandrekas, D.Meade, and.
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.
Role of thermal instabilities and anomalous transport in the density limit M.Z.Tokar, F.A.Kelly, Y.Liang, X.Loozen Institut für Plasmaphysik, Forschungszentrum.
Numerical Study on Ideal MHD Stability and RWM in Tokamaks Speaker: Yue Liu Dalian University of Technology, China Co-Authors: Li Li, Xinyang Xu, Chao.
Integrated Modeling for Burning Plasmas Workshop (W60) on “Burning Plasma Physics and Simulation 4-5 July 2005, University Campus, Tarragona, Spain Under.
Integrated Plasma Simulations C. E. Kessel Princeton Plasma Physics Laboratory Workshop Toward an Integrated Plasma Simulation Oak Ridge, TN November 7-9,
Presented by Yuji NAKAMURA at US-Japan JIFT Workshop “Theory-Based Modeling and Integrated Simulation of Burning Plasmas” and 21COE Workshop “Plasma Theory”
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
Resistive Modes in CDX-U J. Breslau, W. Park. S. Jardin, R. Kaita – PPPL D. Schnack, S. Kruger – SAIC APS-DPP Annual Meeting Albuquerque, NM October 30,
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.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Reconnection Process in Sawtooth Crash in the Core of Tokamak Plasmas Hyeon K. Park Ulsan National Institute of Science and Technology, Ulsan, Korea National.
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.
Features of Divertor Plasmas in W7-AS
11th IAEA Technical Meeting on H-mode Physics and Transport Barriers" , September, 2007 Tsukuba International Congress Center "EPOCHAL Tsukuba",
Reduction of ELM energy loss by pellet injection for ELM pacing
Influence of energetic ions on neoclassical tearing modes
New Results for Plasma and Coil Configuration Studies
20th IAEA Fusion Energy Conference,
Integrated Modeling for Burning Plasmas
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

1 Integrated Simulation Code for Burning Plasma Analysis T.Ozeki, N.Aiba, N.Hayashi, T.Takizuka, M.Sugihara 2, N.Oyama JAERI 、 ITER-IT 2 IEA Large Tokamak Workshop on Burning Plasma Physics and Simulation, W60 Tarragona, Spain, July 2005

2 Background Burning plasma has very wide scales –Timescales –Spatial scales Complex physics: How is the integrated property? –Turbulence, Transport, MHD, Wave-particle interaction, Plasma- wall interaction, Atomic and molecular physics High freq. wave EC, LH, IC Current diffus. Turbulence Island evolu. MHD event Energy confinement Discharge, Plasma-wall [s] [m] TurbulenceTransport MHD Issues on simulation/evaluation of burning plasma

3 Background Controllability of complex plasmas: How do we control the burning plasma and achieve the high performance? –High confinement, High beta, High bootstrap, High radiation, Suppression of impurity –Controllability of autonomous and burning plasmas Strong coupling of pressure and current profiles:  -heating dominant, bootstrap current dominant To solve these issues: It is not realistic to simulate the whole burning plasma based on the first principle at the present. Modeling and integration of the model are a useful method for the complex burning plasma. JAERI is planning to make the integrated code for the burning plasma analysis.

4

5

6 Burning Plasma Simulation Code Cluster in JAERI Tokamak Preduction and Interpretation Code Time dependent/Steary state analyses 1D transport and 2D equilibrium Matrix Inversion Method for NeoClassical Trans. ECCD/ECH (Ray tracing, Relativistic F-P), NBCD(1 or 2D F-P) 1D transport for each impurities,Radiation: IMPACT Perp. and para. transport in SOL and Divertor, Neutral particles, Impurity transport on SOL/Div. : SOLDOR, NEUT2D, IMPMC Tearing/NTM, High-n ballooning, Low-n: ERATO-J, Low and Mid.-n MARG2D Transport by  -driven instability:OFMC Transport code TOPICS Current Drive Edge Pedestal Impurity Transport Divertor MHDMHD High Energy Behaviour

7 MHD Stability and Modeling MHD BehaviorStabilityModeling Sawtooth High energy particles induced instability Ideal/Resistive m/n=1/1 mode Kadomtsev, Porcelli Model Under consideration Island Evolution Beta Limits/ Disruption ELM Tearing/NTM low n kink high n ballooning Medium n modes high n ballooning Modified Rutherford Eq. ERATO-J Ballooing Eq. MARG2D Ballooning Eq. TAE/EAE/EPM... Particles loss

8 Simulation model of ELM 2DEquilibrium data Finite n mode by MARG2D, High n ballooning 1.5D Transport code: TOPICS 1D transport equations : 1D current diffusion equation : 2D MHD equilibrium : Grad-Shafranov equation ELM model : enhance the transport Eigenvalue and eigenfunction Impurity : C 6+, T imp =T i, assumed profile Z eff ρ = (Φ(ρ)/Φ(1)) 0.5

9 Diffusivities in the transport eqs. : Neoclassical transport : Diffusivity and bootstrap current : Matrix inversion method for Hirshman & Sigmar Formula ( M.Kikuchi, et al., Nucl. Fusion 30(1990)343. ) Neoclassical resistivity : Hirshman & Hawryluk model ( Nucl. Fusion 17(1977)611. ) Anomalous transport : Empirical transport model : constant (=0.18[m 2 /s]) :NBI power Density profile Model of transport: Neoclassical in peripheral region (  >0.9) and anomalous in inside region (  <0.9)  

10 MARG2D: low-n and high-n mode stability code [S.Tokuda, Phys. Plasmas 6 (8) 1999] MARG2D solves the 2D Newcomb equation associated with eigenvalue problem Properties of the code –This method can avoid problems due to the continuum spectrum. –Applicable for high n modes stabilities (more than n=50) –Very short calculation time (~85sec for n=40, NR=2800, NV=280,m=90 by Origin 3800,128cpu) –Results of the stability of n=1 agree with those of ERATO-J

11 ELM Model The stability is examined in each iteration step of TOPICS. –When the plasma is unstable, the thermal diffusivity increases according to the eigen-function. –When the mode becomes stable,  ELM =0. Eigen function of unstable mode of n=7 rr  ii m=

12 Results: Simulation of ELM Parameters –R maj =3.4m, a=0.9m, Ip=1.5MA, Bt=3.5T,  ~1.5,  ~0.2 –Ti edge =300eV, ne edge =1x /m 3, Z eff = –  N ~ , P NB(perp) =8MW, –n=1-10 modes Time(sec) W li q surf li W  i (  >0.9)reduced to N-C level (H-mode transition) n=7 mode becomes unstable (ELM)  Ti (eV) t=

13 Enhancement of  i and degradation of T i t=  ii  t= T i (keV) n=7 mode becomes unstable at The heat conductivity increases according to the eigen function. The pedestal of the ion temperature is degraded. –next, the relaxation of the shoulder appeared.

14 Reduction of p and small change of q During the degradation (t= ), the current density profile does not change very much. The most unstable mode shift to higher n mode.  p q q J(A/m 2 )  t=1.299~1.303 p t=1.30~1.36 Recovery phase

15 Stabilization of the mode and Recovery of Ti After the short period of the ELM crash, –the finite-n MHD mode becomes stable –the evolution of the pedestal restarts. –the pressure gradient locally increases, but the modes remain stable. t= t=1.299

16 Computer system and calculation time Estimated cal. time is 58hour for 100msec simulation for 100  s iteration, using 64PE. PC-Cluster PAC1 6GFlops Parallel computer SGI-VSL3000 6G×64PE=384GFlops TOPICS One step CPU ~9sec MARG2D n=1-10 modes CPU 138sec (64PE) CPU 242sec (32PE) (29sec for n=10 only) One iteration cal. ~210sec(64PE) ~300sec(32PE) TOPICS: 9s MARG2D: 138s Communication: 63s Total of 64PE: 210s

17 Summary Integrated simulation for ELMs is realized by the iterative calculation of MHD stability code MARG2D and the transport code TOPICS. Collapse event like ELM is produced. – Degradation and evolution of the pedestal structure are reproduced. Future work –Improvement of the model by the comparison with the experiment: profiles and time-dependent behavior of p and j, MHD and pedestal width etc. –Analysis of the mechanism of ELM events –Clarify the parameter dependency on ELM and give the guideline of control of ELM

18 Discussion "where are we, where do we want to go, how do we get there” –Integrated modeling is a quite realistic simulation; such as real shape, real time scale, and real device parameters. –Usually the modeling uses some assumptions, then integrated modeling is seems to be the integrated assumption. Keeping the physics is the key point. –The validation of the model is important; comparison with the experiments. –Each integrated modeling and simulation should be focused on the issues what we want to know, for example, ELM effects on the burning plasma, …. –It is important to select the physics issues, the control issues, scenarios…