Post on 11-Jan-2016
description
1
M. Yagi1),2)
APFA2011, Guilin, China Nov. 3 2011
Prospects for Fusion Simulation Research
using BA IFERC-CSC
Japan Atomic Energy Agency
1) Plasma Theory and Simulation Group
Division of Advanced Plasma Research
Fusion Research and Development Directorate
2) Research Institute for Applied Mechanics, Kyushu University
Acknowledgement
2
Plasma theory and Simulation Group (JAEA)
JT60 Plasma Design Group (JAEA)
and Drs. T. Ozeki, M. Mori, Y. Koide, T. Nishitani
Drs. K. Shimizu, M. Honda, N. Hayashi, T. Fujita
Drs. Y. Ishii, Y. Idomura, N. Miyato, N. Aiba, M. Hirota,
J. Shiraishi, A. Bierwage, M. Nakata
Profs. A. Fukuyama (Kyoto Univ.), T. Takizuka (Osaka Univ.),
N. Nakajima (NIFS, IFERC)
Contents
BA IFERC-CSC
BPSI (Burning Plasma Simulation Initiative)
NEXT(Numerical EXperiment Tokamak)
Prospects for Fusion Simulation Research using
BA-IFERC-CSC
3
4
Broader Approach (BA) ActivitiesIn parallel to the ITER program, BA activities are being implemented by the EU and Japan,
aiming at early realization of the fusion energy
Naka
Cadarache
Rokkasho
5
Rokkasho BA site
JAPAN
Tokyo
Fukushima
Aomori Pref.
http://map.google.co.jp
Rokkasho
Aomori City
BA Site
Pacific Ocean
Rokkasho BA site
Naka site
6
6
IFMIF/EVEDA
Accelerator Bldg
IFMIF/EVEDA
Accelerator Bldg
Computer Simulation &
Remote Experimental Bldg
Computer Simulation &
Remote Experimental BldgDEMO R&D BldgDEMO R&D BldgAdministration &
Research Bldg
Administration &
Research Bldg
Rokkasho BA site Constructions of all buildings were completed by March 2010.
守衛所守衛所
Power Station(30MVA)
Power Station(30MVA)
ITER
Material Behavior
Two-phase
Heat Flow
Contribution to Comprehensive Promotion
of Demo Reactor Development
Demo Reactor
Design
International Fusion Energy Research CenterInternational Fusion Energy Research Center
Computer Simulation CenterComputer Simulation CenterSimulation Research on Burning and Steady State Advanced Plasma Behaviors
for ITER/Satellite Tokamak, Demo Reactor Design, Advanced Fusion Material Development, etc
Effective and Efficient Promotion of ITER Project and early Realization of
Fusion Power Plant
Satellite Tokamak
~1.3PF Super Computer
Plasma
Behavior
Burning Plasma Prediction
Burning Plasma Prediction
Advanced Plasma Data
Advanced Plasma Data
Verification of Prediction
Verification of Prediction
Design Validation
Design ValidationRequired Conditions of
Demo Reactor Design
Required Conditions of
Demo Reactor Design
8
BPSI (Burning Plasma Simulation Initiative)
9
10
NEXT
BPSI
11
12
3.43.33.23.13.02.9time (s)
0
1000
15
10
5
nid (
1019
m-3)
Ted
(eV
)
3.43.33.23.13.02.9time (s)
0
200
100n
i,SO
L (
1019
m-3)
Te,
SO
L (
eV)
0
2
1
Time evolution of ion density and temperature (nid, Ted) at outer divertor strike point and (ni,SOL, Te,SOL) at outer mid-plane through the L/H transition.
Time evolution of D and Profiles by SONIC
D (a.u.)
03.43.33.23.13.02.9
1.0
time (s)
Temporal fluctuation of SOL/divertor-plasma is observed in H-mode phase.
Simulation of L-H Transition by TOPICS-IB+SONIC
M. Yagi et al
(PET13,2011)
13
NEXT(Numerical EXperiment of Tokamak)
Understanding the complex properties of fusion plasmas and predicting the physical processes in the next generation of tokamaks, such as ITER, using recently advanced computer resources.
To achieve our project, we are developing numerical simulation codes which are applicable for prediction of properties of the core plasma and the divertor plasma on equal footing.
GT5D, MINERVA,GPicMHD,ETC-Rel,PARASOL,SONIC, etc.
Objective:
1414
Code Development in NEXT Project
1996 2001 2006 20111st mid-term
research plan
2nd mid-term
research plan
GT3DPlasma Turbulence GT5D
MHD(LN) MARG2D MINERVA
GYR3DMHD(Non LN) GPicMHD
Runaway Electron ETC-Rel
PIC,Delta-f Vlasov,Full-f
w flow
Rectangular
Up-down symmetry
Cylinder
Non-symmetry
SOL/Divertor
wo flow
1st term 2nd term 3rd term
PARASOL1D PARASOL2DSlab Separatrix ToroidalSOLDOR
+NEUT2D
IMPMCSONIC
G3D
Slab,PIC,Delta-f
15Nonlinear MHD
Variational Principle
Lagrangian approach to resonant three-mode interaction in
magnetohydrodynamics:
ex. Nonlinear behavior of Alfven eigen-mode
Nonlinear simulation of high energy particle driven MHD mode by MEGA and HMGC codes
ex. EPM simulation
Abrupt growth of magnetic island by external perturbation by RMHD model
HMGC EPM calculationDumping rate by three wave coupling of GAE
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Gyrokinetic Toroidal 5D full-f Eulerian code GT5D
GT5D code Global full-f gyrokinetic simulations of turbulent
transport in ITG-TEM turbulence 5D Eulerian code based on non-dissipative
conservative FD scheme [Idomura,JCP07]
Verification [Idomura,CPC08,Satake,CPC10,Camenen,NF10] ITG-TEM benchmark (GT3D,GKW,etc…) Neoclassical benchmark (FORTEC-3D)
Validation
[Idomura,NF09,IAEA10,Jolliet,IAEA10] Avalanche-like non-local ion heat transport Stiffness of ion temperature profile Formation of intrinsic rotation Scaling studies on *, safety factor, rotation
Ti
ITG mode in JT-60SA
with ITER like shape
[Idomura, Comput.Phys.Commun. (2008); Nucl. Fusion (2009)]
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Code extensionTargeted for ITER, JT-60SA equilibrium
(up-down asymmetric equilibrium)Inclusion of vacuum region ( open field lines )Secondary electron, gamma ray emissions,
and material damage due to collision between
runaway electron and structural material
Objective:
Evaluation of first wall damage due to
runaway electrons generated by disruption
Runaway Electron Simulation Code
Code integration by coupling
with disruption coderunaway generation during
current quench phaseenhancement of runaway
electron due to Avalanche
At present: code only solves plasma region with up-down symmetric equilibrium described by Boozer coordinate system
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Prospects for Fusion Simulation Research using IFERC-CSC
● Plasma turbulence: improvement of GT5D code (multi-spices, extension of GK model)
Realization of large scale and high performance turbulence simulation targeted for JT-60 sized device
● MHD: extension to kinetic or extended MHD model
Realization of linear/nonlinear simulation of energetic particle driven mode such as TAE,EPM, EWM etc.
● Disruption: development of integrated Disruption code
including core, SOL/Divertor and conducting wall(error magnetic field)
Realization of vertical Disruption with self-consistent MHD interactions
● Plasma turbulence: improvement of GT5D code (multi-spices, extension of GK model)
Realization of large scale and high performance turbulence simulation targeted for JT-60 sized device
● MHD: extension to kinetic or extended MHD model
Realization of linear/nonlinear simulation of energetic particle driven mode such as TAE,EPM, EWM etc.
● Disruption: development of integrated Disruption code
including core, SOL/Divertor and conducting wall(error magnetic field)
Realization of vertical Disruption with self-consistent MHD interactions
Contributions by Plasma Simulation and Theory Group in JAEA
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Summary
BA IFERC-CSC is implemented by EU and Japan.
Mission : To offer computer resource for large-scale and high
performance fusion simulations aiming for effective and efficient
promotion of ITER project and early realization of fusion power plant.
BPSI is national integrated modeling activity in Japan.
Objective: Establishment of quantitative description of burning
plasmas in ITER. NEXT is numerical experiment of Tokamak project in JAEA.
Objective: Understanding complex properties of fusion plasmas
and prediction physical processes in next generation Tokamaks
such as ITER and JT60SA.
BPSI and NEXT (two halves of the whole, 唇歯輔車 ) will contribute large-scale fusion simulation research making use of BA IFERC-CSC computer resource.
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Thank you for your attention !
謝謝
21
IFERC ProjectFusion Computational Simulation
Centre Coordination
2016201520142013201220112010200920082007
PHASE ONEPHASE ONE PHASE TWOPHASE TWO
SWGs (Special Working Groups)
OperationOperationProcurement Process: On ScheduleInstallation
Procurement
SWG-1
SWG-2Standing Committee
Based on PAs between IAs ( JAEA,F4E ) , resources are provided. EU-IA : Procurement of super-computer for CSC, Operation
and maintenance JA-IA: Building and Electricity for CSC.
2010/4 PA for IT Equipment of CSC 2010/6 Start of Procurement by F4E(CEA) 2011/3 Bull (France) was chosen as Provider 2011/8 Start of Installation
Computational Simulation Center (CSC)
EU-IA(F4E) JA-IA ( JAEA )
PT
Resources(Device, Equipment, Staff etc)
PA
Appendix 1
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IFERC PL
CSC Management
CSC Support TeamVendor Team
StC
allocation of the CSC HPC resource
to adopted projects
technical information about
the CSC HPC operation
report for SC
IFERC PC
Report to PC
Standing Committee (StC)
5 committee members from each side (JA and EU) Tenure of office is 2~3 years StC meeting will be held once in a year by turns Based on distribution of computer resource by StC,
CSC Team will operate and maintain IFERC-CSC HPC
Project Organization Appendix 2
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Appendix 3
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Physics Research in NEXT Project
TurbulenceETG, Streamer
ZF,GAM
ITG, Avalanche
GK Model w Flow
MHD ( Linear) Stability (RS )
MHD(Nonlinear)
Nonlinear Double Tearing ModeSpontaneous
ReconnectionForced
Reconnection
Turbulence Statistics
Disruption (RS)
Pee l ing/Ballooning Mode
Resistive Wall Mode
Matching Theory for Rotating Plasma
Lagrangian Variational Principle
EPM,TAE
Collisionless Kink
ETG, ZF, K-H
1996 2001 2006 20111st mid-term
research plan
2nd mid-term
research plan
1st term 2nd term 3rd term
Appendix 4