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

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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

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )2

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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.

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

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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”

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )4

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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

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )5

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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)

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )6

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

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

In Support of ITER operation

Complementary to ITER operation

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

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )7

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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)

In Support of ITER operation

Complementary to ITER operation

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )8

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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

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )9

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Thank You

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )10

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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

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

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

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

In Support of ITER operation

Complementary to ITER operation

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )11

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M5:Predicting Fusion Performance

*

*

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

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

Gap: Operation at ITER relevant low * and low *

EFDA meeting on EU contribution to JT60SA Research plan version 3 (ENEA Frascati 23-24 may 2011 Aula B Brunelli )12

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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

In Support of ITER operation

Complementary to ITER operation