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- ITALY 1
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 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
Machine Parameters Basic machine parameters Plasma Current 5.5 MA P-NBI Cryostat P-NBI Toroidal Field, B t 2.25 T Major Radius, R p 2.96 ECH Minor Radius, a 1.18 Elongation, X 1.95 Triangularity, X 0.53 Aspect Ratio, A 2.5 N-NBI Shape Parameter, S 6.7 Safety Factor, q 95 ~3 Flattop Duration 100 s Heating & CD Power 41 MW N-NBI 10 MW P-NBI 24 MW ECRF 7 MW Divertor wall load 15 MW/m 2
Sharing
Progress since 2016 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
JT-60SA timeline 18 TF + 6EF coils Mar., 2013 Cryostat Base TF Coil Cold Test Facility Jan., 2014 Lower Poloidal Field Coils Aug., 2015 Sep., 2016 Aug., 2018 Vacuum Vessel VV thermal shield TF Coils Upper Poloidal Field Coils and Central Solenoid JT-60SA Cryostat Current Lead Cryostat QPC TF Coils power supplies MG SCMP S SNU cryoplant NBI First Plasma Sep. 2020 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, total 52mm/13 lines) in toroidal direction. Aug. 2015 10 m 110 Block 6.4mm D07 D09 6.4mm D01 D08 2.4mm D06 D02 D05 D03 D04 120 Block welding 2.4mm 110 Block direct welding D07 D09 D08 D01 340 D06 Splice-plate welding D02 D03 D05 D04 Sector connection by direct welding and splice-plate welding. 6.6 m Requirement Achieved Inboard ±10 mm ±4 mm Outboard ±10 mm +8/-2 mm High dimensional accuracy was achieved 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-cooled monoblock, 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 center from exact circle Achieved CS2 module 1.6m 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. 1.6m 2.0m CS3 module EF1 EF2 EF3 EF4 EF5 EF6 CS1 CS2 CS3 CS4 0.3 mm 0.4 mm 0.2 mm 0.6 mm 0.6 mm 1.3 mm 0.3 mm 0.4 mm 0.4 mm 0.4 mm
TF Coils 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 JT-60SA ITER JET
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 after quench 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.:loading at Vatry Airport 21 st Feb. At Naka 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
Assembly: Final sector inserted 23
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 The cryogenic system was completed by Oct. 2016. Cryolines, all Valve Boxes(VB),all Coil Terminal Boxes(CTB) fabricated. 25
Cryostat Vessel Body Cryostat Top Lid, Delivery to Naka in Sep. 2019. Cylindrical Section: completed
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 27
Magnet PS ~ close to completion C.R.FRASCATI- ITALY (20 ka, 5 kv) C.R.FRASCATI- ITALY Typical PF coil PS circuit (CS1) SNU (High-voltage Generation Circuit) Completion of Magnet PS system is planned in Mar 2019. Quench Protection Circuits (QPC) Switching Network Units (SNU) Superconducting Magnet PSs (Base PS) Booster PSs (reused) Motor Generator (reused) Water Cooling Systems for Magnet PSs Major Component Quantity Current Status CS1 4, EF1 6, TF1 3 13 units Ready for Operation CS1 4 4 units Ready for Operation EF3,4 2 units Ready for Operation EF2 5, TF 5 units Ready for Operation CS1 4, EF1,6 8 units On site Tests on going EF1,2,5,6 H MG 4 units 1 unit Maintenance and Modification ongoing Overhaul Completed, Ready for Operation 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 Controllability of MA-class diverted plasmas BA Phase 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 10 yrs ago to define R&R and common processes, including the sharing of integration functions EURATOM JA Government C.R.FRASCATI- ITALY STP Project Committee Broader Approach Steering Committee (SC) Project Team IPT EU Home Team F4E+CEA+ENEA +CRPP+SCK -CEN +CIEMAT+FZK JA Home Team JAEA
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 Parties o Maintenance/Operation o Scientific Exploitation o Enhancements o And IFMIF/EVEDA (mainly LIPAc in Rokkasho) o And IFERC (DEMO related) IPT Management model to be extended to Research and 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