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Special assignment, OFES, USA1
ClementClement Wong, General Atomics, USAWong, General Atomics, USA
USUS--ITER TBM Meeting, UCLA, ITER TBM Meeting, UCLA, FebruaryFebruary 1414--15, 200715, 2007
TBM Facility Requirements in ITERand Estimated Cost
‘An initial assessment’
A special assignment:At the request from Dr. V. Chuyanov of ITER
and approved by Dr. G. Nardella of OFES
Special assignment, OFES, USA2
ITER, Cadarache, ITER, Cadarache, JanuaryJanuary 26, 200726, 2007
ClementClement Wong, General Atomics, USAWong, General Atomics, USAValery Chuyanov, Chang Shuk Kim, Valery Chuyanov, Chang Shuk Kim,
Alessandro Alessandro TesiniTesini, Markus Iseli, Kimihiro Ioki,, Markus Iseli, Kimihiro Ioki,Manfred Manfred GluglaGlugla, Jerry , Jerry SovkaSovka, ITER, ITER
Otto Bede, KFKIOtto Bede, KFKI--RMKI, RMKI, HungaryHungary
TBM Facility Requirements in ITERand Estimated Cost
‘A very preliminary assessment’
With updates for the Feb 14, 2007 presentation at UCLA
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OutlineOutline• Introduction
• Four TBM and ITER interface areas
1. Port cell2. Hot cell3. TCWS Vault4. Tritium plant
• Cost Estimate
List of items
• Recommendations
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Test of Tritium Breeding Blankets in ITERTest of Tritium Breeding Blankets in ITERTritium Breeding Blankets (BB) are not present in ITER but are necessary in DEMO. The two main functions of BB are:
i) to convert neutron & gamma energy in heat and collect it by mean of an highgrade coolant to reach high conversion efficiency (>30%)
ii) to produce and recover all Tritium required as fuel for D-T reactors Tritiumbreeding self-sufficiency
BB are complex components submitted to very severe working conditions
ITER is an unique opportunity to tests BB mock-ups in a tokamak environment priorthe construction of the DEMO
Test Blanket Modules (TBMs)
It is an ITER mission : “ITER should test tritium breeding module concepts that would lead in a future reactor to tritium self-sufficiency, the extraction of high grade heat and electricity production.”(ITER SWG Report to the IC)
TBMs have to be representative of a DEMO breeding blanket, capable of ensuringtritium-breeding self-sufficiency using high-grade coolants for electricity production
The ITER TBM Program is therefore a central element in the plans of all seven ITERParties for the development of tritium breeding and power extraction technology.
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TBMsTBMs Arrangement in ITER and Interfaces AREASArrangement in ITER and Interfaces AREAS
Additional resources required for adaptation of present ITER building and preparation of ITER/TBM systems interfaces and for accepting/ running TBM systems tests in ITER common cost to be determined by ITER and to be shared by all Parties willing to participate to the TBM program (need of agreement on cost sharing, procedures, coordination by ITER?, others…)
By Luciano Giancarli, chair of TBWGAt the kick-off meeting of the AHG/TBM July 10, 2006
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The TBMs first wall is recessed of 50 mm and protected with a 2 mm Be layer
Shield plug
Frame
TBMLocation
TBM
TBMs tests need a whole TBM system
TBMs Arrangement in ITER and Interfaces AreasTBMs Arrangement in ITER and Interfaces Areas
TBM ports
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TBMsTBMs Design Proposals by ITER Parties for Design Proposals by ITER Parties for dayday--oneone
List of presented TBM Design Proposals for day-one (DDDs also available)
Helium-cooled Lithium-Lead TBM (1 design, F/MS struct.)Dual-coolant (He+Lithium-Lead) TBM (2 designs, F/MS struct.)He-cooled Ceramic Breeder/Be multiplier TBM (4 designs, F/MS struct.)Water-cooled Ceramic Breeder/Be multiplier TBM (1 design, F/MS struct.)He-cooled Liquid Lithium TBM (1 design, F/MS struct.)Self-cooled Liquid Lithium TBM (1 design, V-alloy struct.)
Selection of the coolant connections at each of the 3 ITER test ports based on the TBM proposals
System type Test Port nb. 16 Test Port nb. 18 Test Port nb. 2 He-coolant 2 lines 2 lines 3 lines H2O-coolant - 1 line - ITER heat rejection system
available available available
He purge gas 4 lines 4 lines 4 lines ITER component cooling system
1 line 1 line 1 line
12
3
4 58
67
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Four Interface AreasFour Interface Areas
Ancillary Equipment
1. Port Cell
2. Hot Cell
3. TCWS Vault
EU HCPB helium system
TBM Port Plug
Cooling lines
4. Tritium Plant
Port plug cask
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1. Port Cell Area: replacement of TBM1. Port Cell Area: replacement of TBMTBM Removal from the machine:Step 1: Disconnect port plug and ancillary equipment and
move the ancillary equipment unit (AEU) to its maintenance area (yet to be defined).
Step 2: Bring in the transfer cask, extract the port plug to the transfer cask and move them to hot cell area.
Step 3: Move and insert the port plug into the hot cell “red zone” area.
Step 4: Maintain or replace the TBM and maintain or refurbish the AEU in its maintenance area.
TBM Return to the machine:Step 5: Test the TBM and AEU with the testing utilities.Step 6: Disconnect utilities, insert the port plug to the transfer
cask and return them to the port cell.Step 7: Insert port plug, move the transfer cask away, move in
the AEU and reconnect TBM (port plug) with the AEU.
AEU TBM transfer cask
Cutting and re-welding of PbLi pipes on the AEU will be done in a temporary tent
Hot cell area
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TBM Maintenance: After DTBM Maintenance: After D--T plasma before TBM exchangeT plasma before TBM exchange
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2. Hot Cell Area2. Hot Cell Area
Utilities: e.g. AC/DC, water, high pressure helium, diagnostics…etc., for the testing of TBM and ancillary equipment
Needs additional
• Hot cell “red zone” windows and services• RH equipment• Hot cell area for ancillary equipment maintenance• Utilities for TBM and ancillary equipment tests
Could be parked and maintained here withIncreased area (TBD)
AEU
Special assignment, OFES, USA12
Tokamak Bldg, E-W Section
Equatorial Port Level Section View
TBM HTS in TCWS Vault
Level 0.0
Level 18.06
Port Cell Area
TCWS AreaTBM Cooling system
Equipment Room
TBM Ports#2, 18, 16
3. TCWS Vault Area3. TCWS Vault AreaOriginal space
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3. TCWS Vault Area, 3. TCWS Vault Area, concon’’ttNeeds high pressure Helium (8MPa) and water (15.5 MPa) lines from port cell to TCWS and 4 more coolant system areas EU HCPB helium system
B. Possible solution: build from ground up as attachmentor use a separate building
A. From Dr. EzatoThis approach may not be acceptable due to building codeseismic requirementsand interferencewith the assembly hall
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4. Tritium Interface Area4. Tritium Interface Area
Tritium interface schematic
Two sources of tritium:
1. From the breeder and its corresponding purge stream and/or extraction stream.
2. From the tritium that got permeated and contaminating the main coolant stream.
Observations:
• The maximum pulse tritium generation rate isvery small (~2.09 10-6 gm/s) it may be reasonable to assume that the bred tritium could be collected locally by the use of suitable gettering units or traps, which can then be delivered to the tritium plant for analysis.
• ITER tritium group is ready to support the TBM program more detailed specification on coolant purification system (CPS) and tritium extraction system (TES) and accountancy requirements is needed.
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Items included in the cost considerationItems included in the cost considerationPort cell area and lines to TCWS
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Items included in the cost considerationItems included in the cost considerationHot Cell Area
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Items included in the cost considerationItems included in the cost considerationOther tools and TCWS Vault Area
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RecommendationsRecommendations
• Prepare a summary report on this very preliminary assessment• Use the 3 frames, shields and dummy TBM case,
since additional equipment can always be purchased later.• This cost assessment needs to be performed again in detail• Are some of the items already in ITER cost?
Don’t want to double count.• Initiate and complete work in the following areas:
Port Cell: Components design, TBM exchange and maintenance,procedure…etc.
TCWS: Detail TBM cooling system location, design and cooling lines design.
Hot Cell: AEU parking and maintenance (TBD), TBM RH equipment
Tritium Plant: Further specifications from parties and re-assess needs.