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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
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