1 the broader approach projects p. barabaschi f4e garching – 14 apr 2011
Post on 11-Jan-2016
215 Views
Preview:
TRANSCRIPT
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
top related