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

16

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)]

17

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

1818

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

19

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.

20

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

22

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

23

Appendix 3

24

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