1. 1 The Broader Approach Projects P. Barabaschi F4E Garching – 14 Apr 2011

2. 2 Together with IFERC and IFMIF- EVEDA, JT-60SA is part of the « Broader Approach » agreement signed between Euratom and Japan Entered into force in 2007 JT-60SA IFERC IFMIF-EVEDA BA Agreement

3. IFMIFL M H Accelerator (125 mA x 2) Test Cell Beam shape: 200 x 50 mm 2 High(>20 dpa/y, 0.5 L) Medium(>1 dpa/y, 6 L) Low( 8 L) 100 keV HEBT Source 140 mA D + LEBTRFQMEBT RF Power System Half Wave Resonator Superconducting Linac Lithium Target 25 ±1 mm thick, 15 m/s 3 5 MeV 5 MeV 9 14.5 26 40 MeV 9 14.5 26 40 MeV IFMIF (international fusion materials irradiation facility) will be a neutron source based on a stripping reaction between two deuteron beams and a lithium target aimed to generate a fusion reactor relevant radiation environment with a high neutron flux Hence IFMIF will evaluate irradiation performance of the structural materials under fusion typical conditions -> needed for DEMO.

4. Current activities: IFMIF/EVEDA The Engineering Validation and Engineering Design Activities, conducted in the framework of the Broader Approach aim at:  Providing the Engineering Design of IFMIF  Validating the key technologies, more particularly oThe low energy part of the accelerator (very high intensity, D + CW beam) oThe lithium facility (flow, purity, diagnostics) oThe high flux modules (temperature regulation, resistance to irradiation) Strong priority has been put on Validation Activities, through  The Accelerator Prototype  The EVEDA Lithium Test Loop  Two complementary (temperature range) designs of High Flux Test Modules and a Creep fatigue Test Module

5. Administration & Research Building Administration & Research Building IFMIF/EVEDA Accelerator Building IFMIF/EVEDA Computer Simulation & Remote Experimentation Building DEMO R&D Building International Fusion Energy Research Centre All buildings were completed in March 2010

6. Assembly of the EVEDA Lithium Test Loop Facility Building [40m W, 80m L, 33m H ] JAEA Oarai ELiTe Loop construction completed in November 2010 Commissioning undergoingCommissioning undergoing –Successful operation at nominal temperature, nominal flow rate –Next step before experiment: check the velocity in the Target Assembly Start of the experiments: June 2011Start of the experiments: June 2011

7. 7 A combined project of the ITER Satellite Tokamak Program of JA-EU (Broader Approach) and National Centralized Tokamak Program in Japan. Contribute to the early realization of fusion energy by its exploitation to support the exploitation of ITER and research towards DEMO. Support ITER JT-60SA DEMO Complement ITER towards DEMO ITER JT-60SA Objectives

8. 8 8 The New Load Assembly JT-60SAJT-60U ~4m ~2.5m EAST (A=4.25,1 MA) 1.7m 1.1m SST-1 (A=5.5, 0.22 MA) 3.0m JT-60SA(A≥2.5,Ip=5.5 MA) 6.2m ITER (A=3.1,15 MA) KSTAR (A=3.6, 2 MA) 1.8m JT60-U: Copper Coils (1600 T), Ip=4MA, Vp=80m 3 JT60-SA: SC Coils (400 T), Ip=5.5MA, Vp=135m 3

9. 9 Cryostat Power Supplies TF coils&Testing Assembly NBI In-vessel Components Remote Handling Vacuum Vessel Diagnostics Cryogenic System ECRF Compressor Building Water Cooling System CS, EF coils Japan and EU implement in-kind contributions for components. Existing JT-60U facilities will also be utilized.Sharing

10. 10 JT-60SA is a fully superconducting tokamak capable of confining break- even equivalent class high-temperature deuterium plasmas (I p max =5.5 MA) lasting for a duration (typically 100s) longer than the timescales characterizing the key plasma processes, such as current diffusion and particle recycling. JT-60SA should pursue full non-inductive steady-state operations with high  N (> no-wall ideal MHD stability limits). High Beta and Long Pulse

11. 11 JT-60SA will explore the plasma configuration optimization for ITER and DEMO with a wide range of the plasma shape including the shape of ITER, with the capability to produce both single and double null configurations. Ip=5.5MA, Lower Single NullIp=4.6 MA ITER likeIp=5.5MA, Double Null Plasma Shaping

12. 12 Cryostat P-NBI N-NBI ECH P-NBI Basic machine parameters After successful completion of the re-baselining in late 2008, the JT-60SA project was launched with the new design with the following parameters. Machine Parameters

13. 13 Positive-ion-source NB 85keV 12units x 2MW=24MW COx2u, 4MW CTRx2u, 4MW Perpx8u, 16MW Negative-ion-source NB 500keV, 10MW for off-axis NBCD Variety of heating/current-drive/ momentum-input combinations ECRF: 110GHz, 7MW x 100s 9 Gyrotrons, 4 Launchers with movable mirror NB: 34MWx100s Heating and CD Systems

14. 14Magnet All SC Magnet 18 TF Coils 6 EF Coils 4 CS modules

15. 15 TFC Procurement Conductor Samples Tested successfully (1 from France, 1 from Italy) Detailed Technical Specifications completed Contracts for strand and conductor placed Tenders for coils underway

16. 16 TFC Cold Tests All TFC will be cold (4.5K) tested at full current before shipping to Japan Test Facility will be in CEA-Saclay PA prepared with test facility specifications and cold testing specifications  HV Tests  Leak Tests  Flow, Pressure Drop  Dimensional Stability during and after cooldown  Resistance, Joints  Tmargin, Quench tests (2 coils) Cryostat and jigs being fabricated. Cryostat to be delivered in Saclay in first half 2011

17. CTF Cryostat 17

18. 18 (1) PF conductor manufacturing building constructed in March 2009 (2) PF coil manufacturing building constructed in March 2009 JT-60 Two buildings were constructed in Naka Site in 2009. 680 m The first superconducting conductor of 450m for the EF-4 coil has been completed in March 2010. Two large PF coils (EF-1&6 coils) of 12m in diameter will be manufactured in this building because they are too big to be transported by using public road. 12m Jacketing line Winding machine Cable spool area PFC – on site manufacturing

19. 19 Vacuum Vessel Double Walled 18mm+18mm Boronised Water interspace (~160mm) 200C Baking

20. 20 Vacuum Vessel (2) First Sector to be Delivered in mid March 2011 in Naka

21. 21 Error Field Correction Coil (EFCC) toroidal 6 x poloidal 2 coils (TBD) 30kAT (TBD) frequency ~100Hz (TBD) RMP for ELM control Error Field Correction Coil (EFCC) toroidal 6 x poloidal 2 coils (TBD) 30kAT (TBD) frequency ~100Hz (TBD) RMP for ELM control Fast Position Control Coil (FPCC) upper and lower coils 120kATurn time response <10ms VDE Fast Position Control Coil (FPCC) upper and lower coils 120kATurn time response <10ms VDE RWM control Coil (RWMC) toroidal 6 x poloidal 3 coils (TBD) 20kAT (TBD) RWM control Coil (RWMC) toroidal 6 x poloidal 3 coils (TBD) 20kAT (TBD) Stabilizing Plate SUS316L Double Shell VDE & RWM Stabilizing Plate SUS316L Double Shell VDE & RWM MHD Control in-vessel components

22. 22Cryostat Two parts (~650 Tonnes):  Main machine support  Cylindrical and lid Procurement of Base started. Contract placed. Material procurement underway. Welding trials First component to be installed in torus hall. Delivery in Naka planned for Mid 2012

23. 23 Fully water cooled PFC, in which CFC monoblock targets are partially installed. Carbon tiles are bolted on cooled heat sinks. RH compliant divertor cassette is adopted for future maintenance. Outer Baffle ： 0.3 ～ 1MW/m 2 Bolted CFC and Graphite tiles Outer target (40 degree):10 ～ 15MW/m 2 CFC monoblock target Divertor cassette Outer target:1 ～ 10*MW/m 2 Bolted CFC tiles exchanged by hand in hot-cell Cover for Pipe Connection ： 0.3MW/m 2 Bolted Graphite tiles exchanged by RH CFC (type I and II) materials at the first stage were delivered at Naka in March 2009. Development of the divertor target is in progress to examine brazing for the divertor target. Divertor Cassette

24. 24 High Voltage Deck of N-NBI Torus Hall Assembly Hall Neutron Shielding Wall 24 Mar. 2010 Sep. 2010 JT-60 Disassembly underway

25. 25 Exploitation within the BA period will aim at the initial research phase: - HH operation for plasma full commissioning - DD operation for identification of the issues in preparation for full DD operation Principles of “Joint Exploitation” later phases agreed between EU and JA Detailed “Research Plan” jointly prepared Phased Research Plan

26. 26 -Start of Tokamak Assembly: Early 2012 -Completion of Tokamak Assembly: October 2015 -First Plasma: Mid 2016. Baseline Schedule

27. 27 The BA activities are underway since 3 years IFERC: Supercomputer to start operation in 2012 IFMIF/EVEDA: Prototype accelerator construction underway. Start of operations in 2014. IFMIF Design underway – intermediate report to be available in 2013 JT-60SA: rebaselining undergone in 2008 in order to reduce costs while maintaining its objectives The procurement for the components has progressed with relevant contracts following the PAs for the supply of PF coils, vacuum vessel and divertor by Japan and power supply, cryostat, current leads and TF magnet by EU. The majority of the PAs are either signed or in final preparation JT-60SA research plan has already started to be jointly developed between EU and JA for future exploitation in JT- 60SA. Baseline schedule First Plasma in 2016Conclusions