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Progress of the JT-60SA ProjectP. Barabaschi, Y. Kamada, H. Shirai

For the JT-60SA Integrated Project TeamEU: F4E-CEA-ENEA-CNR/RFX-KIT-CIEMAT-SCKCEN

JA: QST

C.R.FRASCATI- ITALY

JT-60SA Project

1. Support ITERusing break- even- equivalent class high temperature D-plasmas lasting for a duration (typically 100s)

•2. Supplement ITER toward DEMO•with long sustainment (~100s) of high pressure steady-state •plasmas necessary in DEMO

•3. Foster Next Generation •playing leading roles in ITER & DEMO

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

Cryostat

P-NBI

N-NBI

ECH

P-NBIBasic machine parameters

Plasma Current 5.5 MAToroidal Field, Bt 2.25 TMajor Radius, Rp 2.96Minor Radius, a 1.18Elongation, X 1.95

Triangularity, X 0.53Aspect Ratio, A 2.5

Shape Parameter, S 6.7Safety Factor, q95 ~3Flattop Duration 100 s

Heating & CD Power 41 MWN-NBI 10 MWP-NBI 24 MWECRF 7 MW

Divertor wall load 15 MW/m２

Machine Parameters

Sharing

• Procurement and delivery largely completed

• All TF coils tested, delivered

• Basic Torus Assembly Completed

• Individual commissioning of many plant systems completed

• Integrated Commissioning started

• Preparing plans for enhancements and operation

Progress since 2016

JT-60SA timeline

JT-60SA

CryostatBase

Lower Poloidal Field Coils

Vacuum Vessel

VV thermal shield TF Coils Upper Poloidal

Field Coils and Central Solenoid

Cryostat

Mar., 2013

SNUSCMPS

MG diagnostics, etcECRFNBIpower supplies cryoplantFirst Plasma Sep. 2020

TF Coil Cold Test

Facility

QPC

TF Coils

Aug., 2015 Sep., 2016 Aug., 2018Jan., 2014

18 TF + 6EF coils

Current Lead

Cryostat

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

6.6 m

Vacuum Vessel closed with high accuracy

VV Assembly was taken account of welding shrinkage (4mm/line, total 52mm/13 lines) in toroidal direction.

6.4mm

6.4mm

2.4mm

2.4mm

120°Block

110° Block

110° BlockD06

D07

D01

D09

D02

D03

D04

D08D05

D06

D07

D01

D09

D02

D03

D04

D08D05

340°welding10 m

• Sector connection by direct welding and splice-plate welding.

High dimensional accuracy was achieved by careful welding work.

Requirement AchievedInboard ≤ ±10 mm ±4 mm

Outboard ≤ ±10 mm +8/-2 mm

Splice-plate weldingdirect welding

Aug. 2015

JT-60SA in-vessel components

Cryopump

Upper divertor= Open, active-cooled CFC

Lower divertor= ITER-shaped,active-cooled monoblock,

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

RWM Control coil: 18 coils

Fast Plasma Position Control coil 18 Error Field Correction Coils

Stabilizing Plate

MGI valves as DMS

EF & CS: SC coils with high accuracy (~10-4) winding

Achieved

EF1 0.3 mm

EF2 0.4 mm

EF3 0.2 mm

EF4 0.6 mm

EF5 0.6 mm

EF6 1.3 mm

CS1 0.3 mm

CS2 0.4 mm

CS3 0.4 mm

CS4 0.4 mm

Deviation of current center from exact circle

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.

2.0mCS2 module

CS4 module CS1 module CS3 module

1.6m

2.0m1.

6m

TF Coils

JT-60SA

JET

ITER

• Cable in Conduit Conductor , 72 turns, 25.7kA each• 6 double pancakes, 6 turns/pancake. Helium inlets in high

field side – joints in external low field side• Windings enclosed in steel casings• Steel casings inboard wedged, connected in inboard

curved regions by “Inner Intercoil Structure”• Steel casings sliding radially but supported toroidally by

“Outer Intercoil Structure”

Design concept

TF Coils: Cold testing concluded

Cryostat and valve box

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 after

quench tests• Quench test, Tcs<7.47 consistent and in accordance to predictions• Hydraulic flow resistance tests

Air Transportation of last 2 TF coils

21st Feb. At Naka

15 Feb.:loadingat Vatry Airport

17 Feb at Nagoya airport

Assembly: Standing & lifting

Assembly: Rotation

Assembly: Inner Intercoil Structures

Assembly: Outer Intercoil Structure

Assembly: 20° gap for final sector insertion

Assembly: Final sector insertion

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Assembly: Final sector inserted

Torus Assembly

• Mechanical assembly of the TF magnet completed in summer 2018

• Assembly considered throughout the design process

• All interfaces adjustable and all machined with respect to winding pack centrelines

• High assembly accuracy helped keep winding pack centreline positions within acceptable limits

Cryogenic System & Cryodistribution system

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• The cryogenic system was completed by Oct. 2016.

• Cryolines, all Valve Boxes(VB) ,all Coil Terminal Boxes(CTB)fabricated.

Cryostat Vessel Body

Cylindrical Section: completed

Cryostat Top Lid, Delivery to Naka in Sep. 2019.

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High Temp Superconductor Current Leads

HTS-CL decreases required capacity of the cryoplant by 20%.

All 26 HTS-CL • Fabricated at KIT• tested at KIT CuLTKa

facility• Delivered in Naka

Magnet PS ~ close to completion

(20 kA, 5 kV)

Typical PF coil PS circuit (CS1)

Major Component Quantity Current Status

Quench Protection Circuits (QPC)

CS1‐4, EF1‐6, TF1‐3 13 units Ready for Operation

Switching Network Units (SNU)

CS1‐4 4 units Ready for Operation

EF3,4 2 units Ready for Operation

Superconducting Magnet PSs (Base PS)

EF2‐5, TF 5 units Ready for Operation

CS1‐4, EF1,6 8 units On‐site Tests on‐going

Booster PSs (reused) EF1,2,5,6 4 units

Maintenance and Modification on-going

Motor‐Generator (reused) H‐MG 1 unit Overhaul 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

Completion of Magnet PS system is planned in Mar 2019.

C.R.FRASCATI- ITALY

SNU(High-voltageGenerationCircuit)

C.R.FRASCATI- ITALY

JT-60SA Research Phases

Operation-1:Integrated Commissioning

+Equilibrium Controllability of MA-class diverted plasmas

BA Phase II

34MW x 100s

IPT StructureBA 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 10 yrs ago to define R&R and common processes, including the sharing of integration functions

C.R.FRASCATI- ITALY

Broader Approach Steering Committee

(SC)

Project Team

EU Home TeamF4E+CEA+ENEA

+CRPP+SCK -CEN +CIEMAT+FZK

JA Home TeamJAEA

STP Project Committee

EURATOM JA Government

IPT

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 technical and 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 prepared

and 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 Research and Operation activities

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• 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

Conclusions

C.R.FRASCATI- ITALY