EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula...

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )1

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Research strategy of JT60SA in view of a Gap analysis and Overview of European and worldwide Tokamak

capabilities to address Programme needs

Outline

• European and World Wide Tokamaks

• JT60-SA Research Objectives and Strategy

• Capability in addressing the Programme needs

• Summary

Duarte Borba


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Major Radius (m)

Pla

sma

Cur

rent

(M

A)

JT60-SA will be a JET class device capable of 5 MA plasmas

Design values

Routine Operation in H-mode

Operation with Tritium

Circular Plasma Cross Section

European and World Wide TokamaksITER 2019 - (DT,SC)JET (DT) 1997 (DT)JET 1994 JT-60U 1991JT-60SA 2014 (SC) Tore Supra 1988 (SC & Circular)AUG 1991EAST 2006 (SC) KSTAR 2007 (SC) D III-D 1986FTU 1990 (Circular)C-Mod 1993TEXTOR 1981 (Circular)HL-2a 2002TCV 1992SST-1 Soon (SC) HT-7 1993 (Circular)NSTX 1999COMPASS 2009MAST 1999FASTST CTF

- Over 150 tokamak were built around the world, of which around 30 are in operation.


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JT60-SA Research objectives and Strategy• Reliable Tokamak operation at high N

– “explorations in ITER- and DEMO-relevant plasma regimes in terms of the non-dimensional parameters (such as the normalized poloidal gyro radius *, the normalized collisionality * and the normalized plasma pressure N)”

• Long Pulse/Steady state operation– “demonstrates the real-time control in long pulse discharges exceeding

the longest time scale governing the plasma system”


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Reliable Tokamak operation

*

N

ITERJET (DT)JETJT-60UJT-60SA Tore Supra

AUGEASTKSTARD III-D FTUC-ModTEXTORHL-2aTCVSST-1HT-7NSTXCOMPASSMASTFASTST CTFOthers (TFTR …)

In Support of ITER operation

Complementary to ITER operation


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FAST (LP)

EAST

KSTAR

ITER

JT60-SA (HC)

FAST (HF)

JT60-SA (LP)

1

1.5

2

2.5

3

3.5

0.001 0.003 0.005 0.007 0.009 0.011

*

N

Current Tokamaks operation domain

H= 0.8 - 1.0n/nG= 0.3 -0.85

Reliable Tokamak operation

Gap: Operation at ITER relevant * and high N

relevant * and high N is important for NTM physics

Explorations in ITER- and DEMO-relevant plasma regimes in terms of the non-dimensional parameters (such as the normalized poloidal gyro radius *, the normalized collisionality * and the normalized plasma pressure N)


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AUGEASTKSTARD III-D FTUC-ModTEXTORHL-2aTCVSST-1HT-7NSTXCOMPASSMASTFASTST CTF

Resistive Time (s)

Pu

lse

(H

eatin

g)

len

gth

(s)

Gap: Operation with pulse length (Heating) >> Resistive Time

R ~ 0.21 Ip R0/Vloop Mikkelsen D.R. 1989 Phys. Fluids B 1 333

pulseR

pulse10R~L/R

Long Pulse/Steady state operation



JT60-SA “demonstrates the real-time control in long pulse discharges exceeding the longest time scale governing the plasma system”


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Burning Plasmas

Gap: Operation at ITER relevant *fast and high fast

*fast ∞1

B a

Te3/2 PRF/NNBI

B2 ne R03

fast^

Nor

mal

ized

Pre

ssur

e of

Fas

t P

artic

les

ITER 85 MW (Alphas)JET (DT) JET 12 MW (ICRH)JT-60U 7 MW (NNBI)JT-60SA 37 MW (NNBI)Tore Supra

AUG 6MW (ICRH)EASTKSTAR D III-D 3 MW (ICRH)FTUC-Mod 6MW (ICRH)TEXTOR 3 MW (ICRH)HL-2aTCVSST-1HT-7NSTXCOMPASSMASTFAST 30 MW (ICRH)ST CTF

∞(NNBI)

(NNBI)

Simulations using at lower *fast

possible using Hydrogen

(Alphas)

(Alphas)

(Alphas)

(ICRH)

(ICRH)

(Alphas)




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SummaryMission In Support of ITER

operationComplementary to ITER operation

M1:Burning Plasmas FAST, JET (Alphas),

JT60-SA (NNBI)

none

M2:Reliable Tokamak operation

JET, AUG JT60-SA (high n)

M3:Compatibility of First Wall Materials

FAST, JET (Be), JT60-SA ST-CTF

M4: Long Pulse/Steady state operation

JT60-SA (pulse= R) ST-CTF, EAST, KSTAR, SST-1

M5:Predicting Fusion Performance

M6:Components for Nuclear Operation

JET (DT) ST-CTF


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Thank You


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M3:Compatibility of First Wall Materials

Stored Energy (kJ) / Major Radius (m)

Po

we

r L

oss

(M

W)

/ Maj

or

Ra

diu

s (m

)

First Wall Loads

Transient Wall Loads


AUGEASTKSTARD III-D FTUC-ModTEXTORHL-2aTCVSST-1HT-7NSTXCOMPASSMASTFASTST CTFOthers

Gap: Operation with DEMO relevant power exhaust parameters and at ITER relevant (transient) wall loads




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M5:Predicting Fusion Performance

*

*


AUGEASTKSTARD III-D FTUC-ModTEXTORHL-2aTCVSST-1HT-7NSTXCOMPASSMASTFASTST CTFOthers (TFTR …)

Gap: Operation at ITER relevant low * and low *


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DD neutrons

M6:Components for Nuclear OperationITERJET (DT)JETJT-60UJT-60SA Tore Supra

AUGEASTKSTARD III-D FTUC-ModTEXTORHL-2aTCVSST-1HT-7NSTXCOMPASSMASTFASTST CTF

Tritium Burn Up (mg/s)

Neu

tro

n W

all

Lo

ad (

MW

/m2 )

DT neutrons

Gap: A large gap exists between the operation of present devices and the requirements in DEMO in term of Nuclear Operation



EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula...

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