Progress of the JT-60SA Project
P. Barabaschi, Y. Kamada, H. Shirai
For the JT-60SA Integrated Project Team
EU: F4E-CEA-ENEA-CNR/RFX-KIT-CIEMAT-SCKCEN
JA: QST

C.R.FRASCATI- ITALY1

JT-60SA Project
Agreement signed in 2007
Redesigned to meet cost targets in 2008-2009
Mission: contribute to early realization of fusion energy by addressing
key physics and engineering issues for ITER and DEMO
1. Support ITER
using break- even- equivalent class hightemperature D-plasmas lasting for aduration (typically 100s)•2. Supplement ITER toward DEMO
•with long sustainment (~100s) of highpressure steady-state•plasmas necessary in DEMO
•3. Foster Next Generation•playing leading roles in ITER & DEMO

Machine Parameters
Cryostat

Basic machine parameters
Plasma Current

5.5 MA

Toroidal Field, Bt
Major Radius, R p

2.25 T
2.96

Minor Radius, a

1.18

Elongation, X

1.95

Triangularity, X

0.53

Aspect Ratio, A

2.5

Shape Parameter, S

6.7

Safety Factor, q 95

~3Flattop Duration

100 s

Heating & CD Power

41 MW

N-NBI

10 MW

P-NBI

24 MW

ECRF

7 MW

Divertor wall load

15 MW/m２P-NBI

ECH

N-NBI

P-NBI

Sharing

Progress since 2016

• Procurement and delivery largely
completed• All TF coils tested, delivered• Basic Torus Assembly Completed• Individual commissioning of many plantsystems completed• Integrated Commissioning started• Preparing plans for enhancements andoperation

JT-60SA timeline
18 TF + 6EF coils

Mar., 2013

Jan., 2014

Aug., 2015

Cryostat
BaseLower Poloidal
Field Coils

VacuumVesselSep., 2016
VV thermal
shieldAug., 2018
TF Coils

TF Coil
Cold Test
Facility

Cryostat

JT-60SA

CryostatCurrent
Lead

TF Coils
QPC

Upper Poloidal
Field Coils andCentral Solenoidpower supplies
MGSCMPSSNUcryoplant

First Plasma Sep. 2020NBI
ECRF diagnostics, etc

Present Status of Tokamak Assembly•••

TF Coils of 18 are successfully assembled with the high accuracy of ±1mm.
EF Coil and port thermal shield are under installation.
VV Closed

Vacuum Vessel closed with high accuracy
 VV Assembly was taken account of welding shrinkage (4mm/line, total52mm/13 lines) in toroidal direction.
2.4mm
direct welding

Splice-plate
welding

110° BlockAug. 2015

D01
D07

10 m120°Block

D02

D01

D03

D02

D07welding

D09
D04

D03

340°

D09D046.4mm
D056.4mm

D082.4mm

D08

D06

D05
D06

110° Block• Sector connection by direct
welding and splice-platewelding.

6.6 m

Requirement

Achieved

Inboard≤ ±10 mm±4 mm

Outboard≤ ±10 mm

+8/-2 mmHigh dimensional accuracy wasachieved by careful welding work.

JT-60SA in-vessel components
Upper divertor= Open, activecooled CFC

FW:Start with Carbon,=> Full metal-coated ~2030

Lower divertor= ITER-shaped,
active-cooledmonoblock,

Cryopump

 Stabilizing Plate Fast Plasma Position Control coil
 18 Error Field Correction Coils
 RWM Control coil: 18 coils
 MGI valves as DMS

EF & CS: SC coils with high accuracy (~10-4) winding
Deviation of current centerfrom exact circle
Achieved

0.3 mm

EF20.4 mm

EF30.2 mm

EF40.6 mm

EF50.6 mm

EF61.3 mm

2.0m

CS10.3 mm

CS3 moduleCS20.4 mm

CS30.4 mm

CS40.4 mm

1.6m

1.6m
CS2 module

EF1

2.0m
CS4 module

CS1 module

6 EF coils : completed by August 2016.
4 CS modules: completed by March 2018.
Integration of 4 CS modules will be finished by December 2018.

TF Coils•••••

Cable in Conduit Conductor , 72 turns, 25.7kA each
6 double pancakes, 6 turns/pancake. Helium inlets in highfield side – joints in external low field sideWindings enclosed in steel casings

ITER

Steel casings inboard wedged, connected in inboard
curved regions by “Inner Intercoil Structure”
Steel casings sliding radially but supported toroidally by“Outer Intercoil Structure”
JT-60SAJET

Design concept

TF Coils: Cold testing concluded
All 18 +2 spare TF coils have been tested• Electrical insulation tests, warm->cold->test->warm• Full current tests , joint resistance (nOhm range), prior and afterquench tests• Quench test, Tcs<7.47 consistent and in accordance to predictions• Hydraulic flow resistance tests

Cryostat and valve box

Air Transportation of last 2 TF coils
15 Feb.:loadingat Vatry Airport

21st Feb. AtNaka

17 Feb at
Nagoyaairport

Assembly: Standing & liftingAssembly: Rotation

Assembly: Inner Intercoil Structures

Assembly: Outer Intercoil Structure

Assembly: 20° gap for final sector insertion

Assembly: Final sector insertion

Assembly: Final sector inserted23

Torus Assembly••••

Mechanical assembly of the TF
magnet completed in summer
2018
Assembly consideredthroughout the design process
All interfaces adjustable and allmachined with respect towinding pack centrelines
High assembly accuracy helped
keep winding pack centreline
positions within acceptablelimits

Cryogenic System & Cryodistribution system• The cryogenic system wascompleted by Oct. 2016.
• Cryolines, all Valve Boxes(VB),all Coil Terminal Boxes(CTB)
fabricated.

25

Cryostat Vessel Body

Cryostat Top Lid, Delivery toNaka in Sep. 2019.

Cylindrical Section: completed

High Temp Superconductor Current Leads
HTS-CL decreases required
capacity of the cryoplant by20%.
All 26 HTS-CL• Fabricated at KIT• tested at KIT CuLTKafacility• Delivered in Naka27

Magnet PS ~ close to completion

C.R.FRASCATI- ITALY

Major Component

C.R.FRASCATI- ITALY(20 kA, 5 kV)

SNU(High-voltage
Generation
Circuit)

Typical PF coil PS circuit (CS1)

Completion of Magnet PS
system is planned in Mar 2019.

Quantity

Current Status

Quench Protection
Circuits (QPC)

CS1‐4, EF1‐6,TF1‐3

13 units

Ready for Operation

Switching Network
Units (SNU)CS1‐44 units

Ready for Operation

EF3,42 units

Ready for Operation

Superconducting
Magnet PSs (Base PS)

EF2‐5, TF

5 units

Ready for Operation

CS1‐4, EF1,68 units

On‐site Tests on‐going

Booster PSs(reused)EF1,2,5,6

4 units

Maintenance andModification ongoing

Motor‐Generator(reused)H‐MG

1 unitOverhaul Completed,
Ready for Operation

Water Cooling Systems
for Magnet PSs

PF, TF

2 units

Ready for Operation

DC Feeders

PF, TF

11 circuits

Ready for Operation

PS Supervisory Control
Systems

PS‐SC, PS‐IPS,PS‐SIS, PS‐PLC

4 units

Development on‐goingJT-60SA Research Phases
Operation-1:Integrated Commissioning+Equilibrium Controllabilityof MA-class diverted
plasmasBAPhase II

34MW x 100s

IPT Structure
BA Agreement foresees•Very limited size central team with mainly coordination functions•Procurement Arrangements signed between Implementing Agencies-> “collaboration” between EU and JA•Considering this arrangement, a Common Management and Quality Program was developed 10yrs ago to define R&R and common processes, including the sharing of integration functions
EURATOM

C.R.FRASCATI- ITALYSTP Project Committee

JA Government

Broader Approach
Steering Committee(SC)
Project TeamEU Home Team
F4E+CEA+ENEA+CRPP+SCK -CEN
+CIEMAT+FZK

IPTJA Home TeamJAEA

Management model worked out well
The IPT
Competent and committed persons from many institutions
A light but integrated set of common processes valid for all
Agile & motivated team able to quickly tackle the many technicaland administrative problems which were encountered
This is a “software” success story which should be valued
as much as the hardware produced
Thank you all in the JT-60SA IPT for your good will and dedication

BA – Phase 2•••BA Agreement does not end in 2020
Scope of additional activities for a further 5 years preparedand under approval by Partieso Maintenance/Operationo Scientific Exploitationo Enhancementso And IFMIF/EVEDA (mainly LIPAc in Rokkasho)o And IFERC (DEMO related)

IPT Management model to be extended to Researchand Operation activities
32

Conclusions
••
•
•
•
•
•

TF Coils tested, delivered, last sector assembled
Overall delivery mostly completed, 90% the credit value accepted
Torus assembly nearly completed
Commissioning underway  First Plasma planned for Sept 2020
IPT Management model successful
JT-60SA research plan elaborated
Onward plans under approval

C.R.FRASCATI- ITALY