The Broader Approach Projects P Barabaschi F 4

The Broader Approach Projects P. Barabaschi F 4 E Garching – 14 Apr 2011 1

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

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. Accelerator (125 m. A x 2) Source Lithium Target 25± 1 mm thick, 15 m/s LEBT MEBT RFQ Half Wave Resonator Superconducting Linac 140 m. A D+ 100 ke. V 5 Me. V 9 14. 5 26 Test Cell HEBT H M L 40 Me. V Beam shape: High (>20 dpa/y, 0. 5 L) 200 x 50 mm 2 RF Power System 3 Medium (>1 dpa/y, 6 L) Low (<1 dpa/y, > 8 L)

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

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

Assembly of the EVEDA Lithium Test Loop Facility Building [40 m. W, 80 m. L, 33 m. H] JAEA Oarai • Commissioning 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 2011 ELi. Te Loop construction completed in November 2010

JT-60 SA Objectives • 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. ITER DEMO Complement ITER towards DEMO Support ITER JT-60 SA 7

The New Load Assembly • JT 60 -U: Copper Coils (1600 T), Ip=4 MA, Vp=80 m 3 • JT 60 -SA: SC Coils (400 T), Ip=5. 5 MA, Vp=135 m 3 JT-60 U JT-60 SA(A≥ 2. 5, Ip=5. 5 MA) 3. 0 m ITER (A=3. 1, 15 MA) 6. 2 m ~2. 5 m ~4 m 1. 8 m 1. 7 m KSTAR (A=3. 6, 2 MA) EAST (A=4. 25, 1 MA) 1. 1 m 8 SST-1 (A=5. 5, 0. 22 MA) 8

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

High Beta and Long Pulse • JT-60 SA is a fully superconducting tokamak capable of confining breakeven equivalent class high-temperature deuterium plasmas (Ipmax=5. 5 MA) lasting for a duration (typically 100 s) longer than the timescales characterizing the key plasma processes, such as current diffusion and particle recycling. • JT-60 SA should pursue full non-inductive steady-state operations with high N (> no-wall ideal MHD stability limits). 10 10

Plasma Shaping • JT-60 SA 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. 11 Ip=5. 5 MA, Lower Single Null Ip=5. 5 MA, Double Null Ip=4. 6 MA ITER like 11

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

Heating and CD Systems Variety of heating/current-drive/ momentum-input combinations NB: 34 MWx 100 s Positive-ion-source NB 85 ke. V 12 units x 2 MW=24 MW COx 2 u, 4 MW CTRx 2 u, 4 MW Perpx 8 u, 16 MW Negative-ion-source NB 500 ke. V, 10 MW for off-axis NBCD ECRF: 110 GHz, 7 MW x 100 s 9 Gyrotrons, 4 Launchers with movable mirror 13 13

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

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

TFC Cold Tests • All TFC will be cold (4. 5 K) 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 Ø Ø Ø 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 16

CTF Cryostat 17

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

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

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

MHD Control in-vessel components Error Field Correction Coil (EFCC) • toroidal 6 x poloidal 2 coils (TBD) • 30 k. AT (TBD) • frequency ~100 Hz (TBD) • RMP for ELM control Fast Position Control Coil (FPCC) • upper and lower coils • 120 k. ATurn • time response <10 ms • VDE RWM control Coil (RWMC) • toroidal 6 x poloidal 3 coils (TBD) • 20 k. AT (TBD) Stabilizing Plate • SUS 316 L • Double Shell • VDE & RWM 21 21

Cryostat • Two parts (~650 Tonnes): Ø Ø • • 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 22

Divertor Cassette Outer Baffle： 0. 3～ 1 MW/m 2 Bolted CFC and Graphite tiles Outer target: 1～ 10*MW/m 2 Bolted CFC tiles exchanged by hand in hot-cell Cover for Pipe Connection： 0. 3 MW/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. Divertor cassette Outer target (40 degree): 10～ 15 MW/m 2 CFC monoblock target • Development of the divertor target is in progress to examine brazing for the divertor target. • Fully water cooled PFC, in which CFC monoblock targets are partially installed. • Carbon tiles are bolted on cooled heat sinks. 23 • RH compliant divertor cassette is adopted for future maintenance. 23

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

Phased Research Plan • 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 25

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

Conclusions • 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-60 SA: • 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-60 SA research plan has already started to be jointly developed between EU and JA for future exploitation in JT 27 60 SA. Baseline schedule First Plasma in 2016 27