1

The Broader Approach Projects The Broader Approach Projects

P. BarabaschiF4E

Garching – 14 Apr 2011

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 AgreementBA Agreement

IFMIFIFMIF

LLMMHH

AcceleratorAccelerator(125 mA x 2)(125 mA x 2)

Test CellTest Cell

Beam shape:Beam shape:200 x 50 mm200 x 50 mm22 HHighigh (>20 dpa/y, 0.5 L)(>20 dpa/y, 0.5 L)

MMediumedium (>1 dpa/y, 6 L)(>1 dpa/y, 6 L)LLowow (<1 dpa/y, > 8 L)(<1 dpa/y, > 8 L)

100 keV100 keV

HEBTHEBTSourceSource

140 mA D140 mA D++

LEBTLEBTRFQRFQ

MEBTMEBT

RF Power SystemRF Power System

Half Wave ResonatorHalf Wave ResonatorSuperconducting LinacSuperconducting Linac

Lithium TargetLithium Target2525±1±1 mm thick, 15 m/s mm thick, 15 m/s

3

5 MeV5 MeV 9 14.5 26 40 MeV9 14.5 26 40 MeV

IFMIF (international fusion materials irradiation facility) will be a neutron source based on 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 stripping reaction between two deuteron beams and a lithium target aimed to generate a fusion reactor relevant radiation environment with a high neutron flux a fusion reactor relevant radiation environment with a high neutron flux

Hence IFMIF will evaluate irradiation performance of the structural materials under fusion Hence IFMIF will evaluate irradiation performance of the structural materials under fusion typical conditions -> needed for DEMO.typical conditions -> needed for DEMO.

Current activities: IFMIF/EVEDACurrent 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

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 The Accelerator Prototype The EVEDA Lithium Test Loop Two complementary (temperature range) designs of High Flux Test

Modules and a Creep fatigue Test Module

Administration & Administration & Research BuildingResearch BuildingAdministration & Administration & Research BuildingResearch Building

IFMIF/EVEDA IFMIF/EVEDA Accelerator Accelerator BBuildinguilding

IFMIF/EVEDA IFMIF/EVEDA Accelerator Accelerator BBuildinguilding

Computer Simulation Computer Simulation &&Remote ExperimentaRemote Experimentattion ion BuildingBuilding

Computer Simulation Computer Simulation &&Remote ExperimentaRemote Experimentattion ion BuildingBuilding DEMO R&D DEMO R&D BBuildinguildingDEMO R&D DEMO R&D BBuildinguilding

International Fusion Energy Research CentreInternational Fusion Energy Research Centre

All buildings were completedAll buildings were completedin March 2010in March 2010

Assembly of the EVEDA Lithium Test LoopAssembly of the EVEDA Lithium Test Loop

Facility Building Facility Building [40m[40mWW, 80m, 80mLL, 33m, 33mHH]]

JAEA Oarai JAEA Oarai

ELiTe Loop construction completed in November 2010ELiTe Loop construction completed in November 2010

• Commissioning undergoingCommissioning undergoing– Successful operation at nominal Successful operation at nominal

temperature, nominal flow ratetemperature, nominal flow rate– Next step before experiment: Next step before experiment:

check the velocity in the Target check the velocity in the Target AssemblyAssembly

• Start of the experiments: June Start of the experiments: June 20112011

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 ObjectivesJT-60SA Objectives

88

The New Load AssemblyThe New Load Assembly

Present J T- 60U NCT device

JT-60SAJT-60U

~4m~2.5m

EAST (A=4.25,1 MA)1.7m

1.1mSST-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=80m3

• JT60-SA: SC Coils (400 T), Ip=5.5MA, Vp=135m3

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.

SharingSharing

1010

• JT-60SA is a fully superconducting tokamak capable of confining break-even equivalent class high-temperature deuterium plasmas (Ip

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 PulseHigh Beta and Long Pulse

1111

• 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 Null Ip=4.6 MA ITER likeIp=5.5MA, Double Null

Plasma ShapingPlasma Shaping

1212

Cryostat

P-NBI

N-NBI

ECH

P-NBIBasic machine parameters

Plasma Current 5.5 MA

Toroidal Field, Bt 2.25 T

Major Radius, Rp 2.96

Minor Radius, a 1.18

Elongation, X 1.95

Triangularity, X 0.53

Aspect Ratio, A 2.5

Shape Parameter, S 6.7

Safety Factor, q95 ~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/m２

• 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 ParametersMachine Parameters

1313

Positive-ion-source NB85keV12units x 2MW=24MWCOx2u, 4MWCTRx2u, 4MWPerpx8u, 16MW

Negative-ion-source NB500keV, 10MWfor 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 SystemsHeating and CD Systems

14

MagnetMagnet

• All SC Magnet

• 18 TF Coils

• 6 EF Coils

• 4 CS modules

15

TFC ProcurementTFC 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

TFC Cold TestsTFC 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

CTF CryostatCTF Cryostat

17

1818

(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 manufacturingPFC – on site manufacturing

19

Vacuum VesselVacuum Vessel

• Double Walled

• 18mm+18mm

• Boronised Water interspace (~160mm)

• 200C Baking

2020

Vacuum Vessel (2)Vacuum Vessel (2)

• First Sector to be Delivered in mid March 2011 in Naka

2121

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 componentsMHD Control in-vessel components

22

CryostatCryostat

• 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

2323

• 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/m2

Bolted CFC and Graphite tiles

Outer target (40 degree):10 ～ 15MW/m2

CFC monoblock target

Divertor cassette

Outer target:1 ～ 10*MW/m2

Bolted CFC tiles exchanged by hand in hot-cell

Cover for Pipe Connection ： 0.3MW/m2

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 CassetteDivertor Cassette

24

High Voltage Deck of N-NBI

Torus HallAssembly Hall

Neutron Shielding Wall

24

Mar. 2010

Sep. 2010

JT-60 Disassembly underwayJT-60 Disassembly underway

25

PhaseExpectedDuration

AnnualNeutron

Limit

RemoteHandling

Divertor P-NB N-NB ECRFMax

PowerPower x Time

ExtendedResearch

Phase>5y D 1.5E21 DN 24MW 41MW 41MW x 100s

phase I

phase II

H

D

1-2 y

2-3y

InitialResearch

Phase

IntegratedResearch

Phase

Use

phase I

phase II

D 4E20

1E21

R&D4E19NB: 20MW x 100s

30MW x 60sduty = 1/30

ECRF: 100s

1.5MWx100s

+1.5MW

x5s

7MW

37MW

33MW

23MW

>2y

LSNpartial

monoblock

LSNfull-

monoblock

10MW

Perp.13MW

Tang.7MW

10MW

D

-

2-3y

• 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 Phased Research Plan

26

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

Baseline ScheduleBaseline Schedule

2727

• 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 2016

ConclusionsConclusions