OV/3-3

Recent Progress of JT-60SA Project
H. Shirai1, P. Barabaschi2, Y. Kamada3 and the JT-60SA
1JT-60SA Project Leader, 2EU Project Manager, 3JA Project Manager

IAEA Fusion Energy Conference 201617-22 October 2016
@Kyoto International Conference Center1

JT-60SA (JT-60 Super Advanced) ProjectJT-60SA Project is implemented under the Broader Approach (BA)
Agreement between EU and Japan as well as the Japanese nationalfusion programme.
Mission:Contribute to the early realization of fusionenergy by addressing key physics andengineering issues for ITER and DEMO.
Major Objectives:(1) Supportive Researches for ITER
JT-60SA starts operation in 2019→ address ITER related issues in advanceand optimize its operation scenarios
under the break-even condition(2) Complementary Researches for DEMO
study long sustainment of high integrated
performance plasmas with high N value(3) Foster Next Generationbuild up experience of young scientists andtechnicians who will play leading roles inITER and DEMO.

15.5m(full current inductive mode)
Plasma Current
5.5 MA
Toroidal Field
2.25 T
Major Radius
2.96 mMinor Radius
1.18 mElongation, X
1.87
Triangularity, X
0.50
Safety factor, q95
3.0Plasma Volume
131 m3
Heating Power
41 MW
Normalized beta, N
3.1

2

JT-60SA target region in relation toITER and DEMO

powerful NBI&ECRFflexible shaping
Full Ip

5.5MA

in-vessel coils

ITER like4.6MA

3Long sustainment of high integrated performance plasmas with high N value for DEMO
will be investigated by making the best use of (1) powerful and versatile NBI&ECRF
system, (2) flexible plasma shaping, (3) various kinds of in-vessel coils, and so forth.

Share of JT-60SA Components and Systems(remarkable progress since the last IAEA FEC)
175t+45t

Cryostatvessel body396t

Toroidal Field
Coils

157t+100t

Poloidal Field
Coils (EFC&CS)

260t

150t

Cryostat base

Vacuum Vessel

Compressor Building

Radio Frequency
Resonance
Heating System

Cryogenic System

In-vessel Components

Plasma12m

Neutral Beam
Injector
Divertor

PlasmaDiagnostics

15.5m

Naka Site
Power Supplies

Existing JT-60 facilities (e.g. transformer substation, motor generators, etc.) arealso reused as much as possible to reduce overall project cost.
4Toroidal Field Coils (NbTi)(1) winding pack (WP) fabrication(4) final machining

18 TF coils plus 2 spare TF
coils are being fabricatedin France and Italy.

(2) impregnation of WP(3) WP enclosed in coil casing(5) completed TF coil

TF coilcross section
NbTi conductor (6 DPs)
(26mmx22mm)

5Two TF coils now in Naka Site(6) performance tests at cryogenic temperature @CEA Saclay(7) OIS preassembly(full current test, quench test, etc.)(8) delivery to Naka Site

2nd coil “Brigitte”
1st coil “Annie”
3rd coil “Roberta”

coming on thePacific Ocean

TF coil assembly around the vacuum vessel will start in December 2016. 6

Equilibrium Field Coils (NbTi)
All EF coils were manufactured with excellent accuracy in the circularity
for minimizing error field.
EF1
EF2
EF3
EF4
EF5EF6Diameter12.0 m
9.6 m
4.4 m
4.4 m
8.1 m
10.5 mCircularity Requirement
0.3 mm≤8 mm
0.4 mm≤7 mm
0.2 mm≤6 mm
0.6 mm≤6 mm
0.6 mm≤7 mm
1.3 mm≤8 mm

12 m

fabrication
Aug. 2016

EF1

9.6 m

Feb. 2013
Jan. 2014

EF2

4.4 m
EF4

EF3
EF5EF6

EF4, EF5 and EF6 are temporally
placed on the Cryostat Base.

7Central Solenoid (Nb3Sn)
JT-60SA has 4 identical Central Solenoids (CS)(1) winding of conductor

One CS module iscomposed of 7 pancakes(6 OP and 1 QP).

(2) insulation and stacking(4) 1st CS module is now in
NIFS waiting for cold test.

(3) impregnation

2m

CS18

High Temperature Superconductor Current Leads,
Coil Terminal Boxes and Valve Boxes
High Temperature Superconductor Current Leads (HTS-CLs) using bismuth
alloy (Bi-2223/AgAu) saves cooling power of the cryogenic system.
(6 HTS-CLs (25.7kA) for TF coils, 20 HTS-CLs (20kA) for EF coils and CS)
external current feeder (60 K)
HTS-CLsuperconducting feeder (4.4 K)

HTS-CLs for TFC

Coil Terminal Box(CTB)

Valve box (VB)
(for cold helium feeding)(for current feeding)
Cryogenic transfer line

(test facility CuLTKa in KIT) 9

Cryogenic Plant has been newly
constructed in the Naka Site.
Refrigerator Cold Box &Auxiliary Cold Box

Helium Storage vessels

Warm Compressors

Construction Work in Naka Site

Naka Site on 7 April 2015

Naka Site on 27 May 201510

Commissioning of the Cryogenic
System was successfully completed.

 Adoption of Auxiliary Cold Box facilitatesheat load smoothing.
 Actual operational condition were tested andvalidated by the commissioning in Sep. 2016.

Cryogenic HallAuxiliary
Cold Box(ACB)

Refrigerator
Cold Box
(RCB)

10000
9000
8000
7000
6000
5000
4000
3000
2000
1000
0

Heat pulse through TFC and PFC
Average load forcryogenic system

heat load (W) The total power equivalent at 4.5K is about
9kW. (world largest class refrigerator for afusion plant before ITER)

0300

Compressor Building

600

900
1200
time (s)

1500

1800

six He gas
storage vessels
LN2 tank

8 warm compressors

11

Fabrication of three cryostat parts
45 ton, 11.6 møCryostat Top Lid

Cryostat Vessel
Body Cylindrical
Section175 ton, 13.5 møCryostat Base(displacement analysis)max. 1.6mm

detailed design completed

260 ton, 12 møassembled in March 2013

under fabrication

12

340° Vacuum Vessel was completed
80° Vacuum Vessel in June 2014
inboardoutboard

340° Vacuum Vessel in Aug. 2015

First delivery of 40° inboard sector in Apr. 201113

Thermal Shields are being installed.
(inside the vacuum vessel)

40° VVTS

6.3 m(inside dimension)in the VVTS
manufacturer

assembly jig for VVTS
outboard VVTS
High dimensional accuracy was achievedby careful welding work.
horizontal
verticalactual±5 mm-4 mm

Requirement±30 mm+6/-4 mm

(Welding shrinkage in the torus direction
was adjusted by welding with splice plates.)

20° gap

vacuumvessel14
VVTS assembly will be completed in Nov. 2016.

Power Supply System
SCMPS (Superconducting Magnet PS)

QPC Shipping(QuenchProtectionCircuit)ready（52 boxes）

Base PS to provide DC current to the SC coilsProtection of SC coils whenquench or PS failure occur

PS for EF2~EF5 and TF coils

10 units for EF coils and CS modules
3 units for TF coils,delivered to Naka in June 2016
PS for CS1-4 modules, EF1,EF6 coilsCommissioning in June 2015

to be delivered in 2017

SNU (Switching Network Unit)
Booster PS to provide high voltage forplasma breakdown and current ramp-up

delivered to Naka in Oct 2016

Motor Generator (reused facility)
Provide power for P-NBI, N-NBI, EF&CS PS
H-MG: 18kV/400MVA, 2.6GJ
T-MG: 18kV/215MVA, 4.0GJ

Overhaul of H-MG was carried out in 201515

Powerful and versatile heating/CDby NBI and ECRF (41MW in total)
ECRF system

NBI system
 P-NBI, 85keV, 12units × 2MW=24MW, 100s
tangential 4u (CO:2u, CTR:2u), Perpendicular: 8u
 N-NBI, 500keV, 2units×5MW=10MW, 100s
tangential, off-axis

various beam
injection angle

 9 Gyrotrons, 4 Launchers
7MW in total<5kHz power modulation
 movable mirror at launcher multi-frequency gyrotron
110GHz(2nd) (1MW,100s) +138GHz(2nd) (1MW,100s) +82GHz(fund.) (1MW, 1s)(start-up assist, wall cleaning)
138 GHz(2nd)NNB

82 GHz(fund.)

110 GHz(2nd)(top view)
Beam acceleration of 85 keV
was successfully demonstrated
for 100s (P-NBI).
(P-NBI ion source)

Heating, current-drive and momentum-input
profiles can be flexibly controlled.

(gyrotron)

Bt = 2.25 T(launcher)16

Overall Progress of JT-60SA Project
Operation starts
in 2019

JT-60SA assembly(Cryostat Base)
EF coils
Mar. 2013

VacuumVessel

TF coils
cold test
facility

We are here!

Jan. 2014
Sep. 2015
Cryostatupper EF coils
lower EF coils Vacuum Vessel(body & top lid)and CS(340 deg.)
VV Thermal
ShieldMagnet interface (HTS-CL)(340 deg.) cryoplant
power supplies
NBI
ECRF diagnostics
QPCSCMPSNU
MG-setS17

Research Phases of JT-60SA
 JT-60SA research phase starts with Hydrogen operation to conduct full commissioning.
 JT-60SA is upgraded step by step.
(power/duration of P-NBI&ECRF, divertor target material, remote handling availability)

ITER
H / Heoperationphase

Possibility ofW-coated full monoblock CFC(partially bulk W) divertor+ full W-coated first wall
+ fully water-cooled

Partially W(or W-coated CFC)
divertor tiles(address compatibility of metallic divertor with integrated high performance plasmas)18

EU/JA Research Collaboration
on JT-60SA Project Research collaboration on JT-60SA Project is strongly promoted.
 EU and JA fusion community members join “JT-60SA Research Unit” to study key
physics and engineering issues of ITER and DEMO.

5th. EU&JA Research Coordination Meeting(May 2016, Naka)

JT-60SA ResearchPlan (ver. 3.3) written
by 378 authors from
EU/JA was open to
public in March 2016.
http://www.jt60sa.org/pdfs/JT-60SA_Res_Plan.pdf
JT-60SA target region coversand DEMO target.
Thus their acceptable parameters will be investigated by JT-60SA operation.

19

JT-60SA as a flexible ‘Test Stand’ for ITER
 ITER like operation environment
ITER like non-dimensional parameters, small-torque input
Electron heating dominant plasma (by N-NBI, ECRF)
Large fraction of energetic particle (500 keV N-NB)
Operation scenario optimization with superconducting coils.
 High Plasma Performance
H-mode operation (H, He, D) study (Ip ~ 5.5 MA) towards Q=10
L-H transition, Pedestal Structure, Confinement Improvement
H-mode compatibility with radiative divertor, RMP, etc.
Confinement in high nGW regime
Effect of Local Ripple, Error Field / noise on confinement
Improved H-mode (Hybrid) operation with ITER-like shape (Ip ~ 4.6 MA)
 Divertor Integrity
ELM mitigation (RMP, pellet pacing, etc.) & small / no ELM regime at low *
Divertor Heat Load reduction (radiative divertor, ITER-like divertor config.)
Disruption avoidance & mitigation at high Ip (MGI, etc. ) High N plasma
MHD instability suppression at small~zero rotation condition20

Research and Development for tokamak
operationTH/P2-19 (N. Hayashi) [Tue.]

EX/P8-31 (D. Douai) [Fri.]

Core-edge coupled predictive modeling ofJT-60SA high-beta steady-state plasma with
impurity accumulation has been studied.

EC Wall Conditioning (ECWC) experiments
to support JT-60SA operation have been
performed by TCV.

← Ar density profile
calculated by SONIC

1.5D core transport
solver (TOPICS) +IMPACT using SONIC
Ar edge densities →Ar seeding is effective
for reduction of divertor
heat load below 10
MW/m2. Ar16-18+
accumulation in corecauses slight decreaseof temperature, which
is fully recoverable byadditional core heating.

ECWC
efficiency
assessed
fromamount of released
D2 fuel →Ion saturation
current profilechanges with
BH and BV . ↓Optimized combination of BH and BV are
required for effective wall conditioning.

see more in EX/P8-40 (G. Giruzzi, M. Yoshida) [Fri.]

21

Summary of JT-60SA Project
1. Fabrication, installation and commissioning of JT-60SA
components and systems procured by EU and Japan are steadily
progressing. TF coil assembly around the vacuum vessel will startsoon. JT-60SA starts operation in 2019.
2. Powerful and versatile NBI/ECRF system, flexible plasma
shaping, various kinds of in-vessel coils are advantage of JT-60SAfor plasma control.
3. JT-60SA will explore ITER and DEMO relevant parameter regionin advance for the purpose of optimization of their operational
scenarios, especially in high N (~5) region.
4. Close research collaboration between EU and Japan has beenpromoted. JT-60SA Research Plan v.3.3 by 378 researchers fromEU and Japan released in March 2016 elaborates on key physics
and engineering issues to be addressed for ITER and DEMO.
22JT-60SA related presentations in this conference
18 Oct (Tue)FIP/1-3Ra (J. Hiratsuka) Long-pulse acceleration of 1MeV negative ion beams toward ITER and JT60SA neutral beam injectors & towards powerful negative ion beams at the test
facility ELISE for the ITER and DEMO NBI system
TH/P1-18 (T. Bolzonella) Securing high N JT-60SA operational space by MHD stability and active
control modelling
TH/P2-19 (N. Hayashi)
Core-edge coupled predictive modeling of JT-60SA high-beta steady-state
plasma with impurity accumulation
TH/P2-20 (M. Romanelli) Investigation of Sustainable Reduced-Power non-inductive Scenarios on JT60SA

19 Oct (Wed)
FIP/P4-42 (C. Day)

Assessment of the operational window for JT-60SA divertor pumping underconsideration of the effects from neutral-neutral collisions

20 Oct (Thu)
TH/P6-24 (R. Zagorski)

Numerical analyses of baseline JT-60SA design concepts with the COREDIV
code

21 Oct (Fri)FIP/P7-37 (J.-C. Vallet)
EX/P8-31 (D. Douai)
EX/P8-40 (G. Giruzzi)
FIP/4-1Ra (Y. Shibama)FIP/4-1Rb (P. Decool)

Towards the completion of the CEA Contributions to the Broader Approach
Projects
Development of Helium Electron Cyclotron Wall Conditioning on TCV for theoperation of JT-60SA
Physics and operation oriented activities in preparation of the JT-60SA
tokamak exploitation
Assembly Technologies of the Superconducting Tokamak on JT-60SA
23JT-60SA TF Coil Manufacture, Test and Preassembly by CEA