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ITPA Topical Group Meeting on Steady State and Energetic Particles St. Petersburg, Russia 2003-07-15 Present Status of ITER Scenario Development Code in Japan A. Fukuyama Kyoto University in collaboration with H. Shirai (JAERI), T. Ozeki (JAERI), T. Takizuka (JAERI) M. Yagi (Kyushu U), N. Nakajima (NIFS), H. Naitou (Yamaguchi U), Y. Nakamura (Kyoto U) Contents Integrated Code Development Transport Simulation by TASK/TR ECCD Analysis by TASK/WR+FP Summay

Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

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Page 1: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

ITPA Topical Group Meetingon Steady State and Energetic Particles

St. Petersburg, Russia2003-07-15

Present Status of ITER Scenario Development Codein Japan

A. FukuyamaKyoto University

in collaboration with

H. Shirai (JAERI), T. Ozeki (JAERI), T. Takizuka (JAERI)M. Yagi (Kyushu U), N. Nakajima (NIFS),

H. Naitou (Yamaguchi U), Y. Nakamura (Kyoto U)

Contents

• Integrated Code Development

• Transport Simulation by TASK/TR

• ECCD Analysis by TASK/WR+FP

• Summay

Page 2: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Integrated Code Development

• Integrated Burning Plasma Simulation Initiative

• Core code: Tokamak Transport Code

◦ TOPICS: JAERI Naka

◦ TASK: Kyoto Univ

• Present status and to do’s in 2003

◦ Benchmark test between TOPICS and TASK

◦ Comparison with JT-60U experimental data (transport models)

◦ Comparison with ITPA profile database

◦ Preliminary simulation of ITER scenario

Page 3: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Objectives

Integrated Simulation of Burning Plasmas

• Frameworkfor collaboration of various plasma simulation

codes• New physics

in interaction between phenomena with differenttime and space scales

• Advanced techniqueof computer science, network computing and

visualization

Page 4: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Framework

• Core Code– Based on Extended 1.5D Transport Code

• TASK/EQ, PL, TR, DP, WR, WM, FP (Kyoto U)– Analysis of Experimental Data (JT-60, ITPA)– Predictive Simulation for Burning Plasmas

• Common Interface for Data Transfer– Working group for interface specification– Interface with existing codes and modules

• Topics (JAERI), NTCC (USA)– Interface with experimental data base

• MDSPlus• Development and Enhancement of Modules• Elaborated User Interface

Page 5: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

New Physics

• Transport-MHD Hierarchical Model– Interaction between MHD and transport phenomena– Consistent modeling with plasma flow– Transport in the presence of magnetic island

• Core-SOL Interface– Modeling of edge transport barrier– Two-dimensional transport in edge region

• Interaction with Energetic Particles

Page 6: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Transport-MHD Model

Page 7: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Advanced Technique

• Parallel Computing– PC cluster– Vector-parallel super computer

• Network Computing– GRID computing– Effective use of computer resources

• Visualization– Parallel visualization– VisiGRID

Page 8: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Integrated Code Development

• Integrated Burning Plasma Simulation Initiative

• Core code: Tokamak Transport Code

◦ TOPICS: JAERI Naka

◦ TASK : Kyoto Univ

• Present status and to do’s in 2003

◦ Benchmark test between TOPICS and TASK

◦ Comparison with JT-60U experimental data (transport models)

◦ Comparison with ITPA profile database

◦ Preliminary simulation of ITER scenario

Page 9: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Structure of TASK code

Page 10: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Integrated Code Development

• Integrated Burning Plasma Simulation Initiative

• Core code: Tokamak Transport Code

◦ TOPICS: JAERI Naka

◦ TASK: Kyoto Univ

• Present status and to do’s in 2003

◦ Benchmark test between TOPICS and TASK

◦ Comparison with JT-60U experimental data (transport models)

◦ Comparison with ITPA profile database

◦ Preliminary simulation of ITER scenario

Page 11: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

CDBM Turbulence Model

• Marginal Stability Condition (γ = 0)

χTB = F(s, α, κ, ωE1)α3/2 c2

ω2pe

vA

qR

Magnetic shear s≡ rq

dqdr

Pressure gradient α ≡ − q2Rdβdr

Magnetic curvature κ ≡ − rR

(1− 1

q2

)

E × B rotation shear ωE1 ≡ r2

svA

ddr

ErB

• Weak and negative magnetic shear,

Shafranov shift and

E × B rotation shear

reduce thermal diffusivity.

s− α dependence ofF(s, α, κ, ωE1)

0.0

0.5

1.0

1.5

2.0

2.5

-0.5 0.0 0.5 1.0

F ωE1

=0.2

ωE1

=0.3

ωE1

=0.1

ωE1

=0

s - α

Fitting Formula

F =

11 + G1ω

2E1

1√2(1− 2s′)(1− 2s′ + 3s′2)

for s′ = s− α < 0

11 + G1ω

2E1

1 + 9√

2s′5/2√2(1− 2s′ + 3s′2 + 2s′3)

for s′ = s− α > 0

Page 12: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Simulation of ITB Formation

Comparison with JT-60U experimental data : on-going

Time Evolution

JT-60U EXP Simulation

t [s]

t [s]

t [s]

t [s]

t [s]

PNBIIp

I p [M

A] P

NB

I [MW

]

WdiaSn

Sn [10 16s -1]

Wdi

a [M

J]

n (0)

|

n (0.7)

|

n e [1

019 m

-3]

Te(0)Ti (0.34a)

T [k

eV]

βN

βNτΕ / τΕITER89-P

τ Ε /

τ ΕIT

ER

89-P

t [s]

t [s]

t [s]

t [s]

t [s]

WB WiWe

Ip IOHIBS

PNBI

ne (0) <ne>

TiTe<Te>

<Ti>

τ1τΕτ2

I p [M

A]

PN

BI [M

W]

Wdi

a [M

J]n e

[101

9 m-3

]T

[keV

Safety Factor

JT-60U EXP Simulation

r / a

q

r [m]

t = 5.2t = 4.4t = 3.6t = 2.8

t = 2.0

q

Ion Temperature

JT-60U EXP Simulation

T [k

eV]

r / a

T [k

eV]

r [m]

t = 2.2

t = 2.8t = 2.7

t = 2.6

t = 2.0t = 2.1

t = 2.5t = 2.4t = 2.3

Page 13: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Simulation of Current Hole Formation

• Current ramp up: Ip = 0.5 −→ 1.0 MA

• Moderate heating: PH = 5 MW

• Current hole is formed.

• The formation is sensitive to the edge temperature.

.1*2+

./-*2+

.,0*2+

.*/+

-0

,0

.*/+

-0

,0

/.*0+

,1

-110.0*2+

1.-*2+

1,/*2+0./*1+

-2

,2

Page 14: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Sustainment of Negative Shear Configuration

Off-Axis CD (H ' 1.2)

PLH/PIC = 12/2 MW

q

qj

[MA

/m2 ]

T [k

eV]

p [M

W/m

3 ]

r [m]

j tot

j LH

j BSj OH

TD

Te

p LH

p IC

Full CD (H ' 1.6)

PLH/PIC = 12/10.8 MW

qj

[MA

/m2 ]

T [k

eV]

p [M

W/m

3 ] p LHp IC

Te

TD

j tot

j LH

j BS

q

r [m]

Full CD + On-Axis CD

PLH/PIC/PEC = 12/10.8/0.2 MW

qj

[MA

/m2 ]

T [k

eV]

p [M

W/m

3 ]

r [m]

p LH

p IC

p EC

Te

TD

j tot

j LH

j BSj EC

q

Page 15: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Analysis of ECCD by TASK Code

Poloidal angle 70◦

Toroidal angle 20◦

Initial beam radius 0.05 mInitial beam curvature 2 m

/ 0 1 2 3,/

,.

-

.

/

5*6

+

4*6+1 2 3 4 5

-0

-/

.

/

0

6+;,

6+;

,

7<= 8:9>

One Ray Nine Rays Beam Tracing

Ray/Beam Profile

+*.+ +*./ +*/+ +*// +*0++

/

,+

,/

-+

5

1234

+*.+ +*./ +*/+ +*// +*0++

/

,+

,/

-+

-/

5

1234

-,- -,/- -,0- -,1- -,2- .,---

-,-/

-,-0

-,-1

-,-2

-,.-

3*4

+

5

PabsProfile

+*.+ +*./ +*/+ +*// +*0++

/

,+

,/

-+ 1234

5+*.+ +*./ +*/+ +*// +*0++

/

,+

,/

-+

-/ 1234

5+*.+ +*./ +*/+ +*// +*0++

/

,+

,/

-+

-/1234

5

jCD Profile

-+0- -+01 -+1- -+11 -+2-

-+--.-

-+---3

-+---2

-+---0

-+---/

-

965

4,:

8/7

;

-+0- -+01 -+1- -+11 -+2--

-+---/

-+---0

-+---2

-+---3

-+--.-

-+--./

965

4,:

8/7

;

-+-0

-+-/

-+-.

--+1- -+12 -+2- -+22 -+3-

;

965

4,:

8/7

Page 16: Present Status of ITER Scenario Development Code in Japanfukuyama/pr/... · Benchmark test between TOPICS and TASK Comparison with JT-60U experimental data (transport models) Comparison

Summary

• Integrated simulation codes, TOPICS and TASK, are under development. Bench-mark test between the codes and comparison with JT-60U data and ITPA profiledatabase in on-going.

• Improvement of physics models, such as interaction between transport and MHDphenomena, and transport model, is also going in parallel.

• Ballooning-type transport model which depends on s − α reproduces ITB andcurrent hole. The formation of the current hole is sensitive to the edge temper-ature through the current penetration time scale. Initial currnet profile control bylocalized edge heating may be possible.

• ECCD in ITER configuration was carried out by beam tracing method. Result ofbenchmark calculation will be reported within a month.