Presented by Scott Willms (LANL) Harnessing Fusion Power Workshop UCLA March 2, 2009
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Transcript of Presented by Scott Willms (LANL) Harnessing Fusion Power Workshop UCLA March 2, 2009
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Presented by
Scott Willms (LANL)
Harnessing Fusion Power Workshop
UCLA
March 2, 2009
Renew Fuel Cycle Panel
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Fuel Cycle Panel Members
– Scott Willms (LANL)– Jim Klein (SRNL)– Alice Ying (UCLA)– Larry Baylor (ORNL)– Martin Peng (ORNL)– Dai-Kai Sze (UCSD)
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Approach: Tie Fuel Cycle back to original Greenwald questions
1. “What R&D thrusts are needed to build DEMO.”
1.1 “What is needed to be able to properly supply and handle tritium for DEMO?”
1.1 How do we close the fusion fuel cycle?
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Seven sub-questions
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Q 1-4
• 1.1.1 What is needed to adequately process fusion fuel for DEMO?
• 1.1.2 What is needed to provide torus vacuum and fueling for DEMO?
• 1.1.3 What is needed to adequately contain and handle tritium for DEMO?
• 1.1.4 What is needed to adequately perform tritium accountability and nuclear facility operations for DEMO?
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Q 5-7
• 1.1.5 What is needed to breed tritium for DEMO?
• 1.1.6 What is needed to extract tritium from the breeding system for DEMO?
• 1.1.7 What is needed to characterize, recover and handle in-vessel tritium for DEMO?
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Backdrop
State-of-the-art6 liters/minTime requirement 24 hr100 gm inventoryDuty cycle: 15%“Power”: 1000 MW
Need for ITER120 liters/minTime requirement 1 hr4000 gm inventoryDuty cycle: 5%Power: 400 MW
DEMO
Need for DEMO500 liters/min?Time requirement 1 hr6000 gm inventoryDuty cycle: 50%Power: 2000 MW
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Detail under each question
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1.1.1 What is needed to adequately process fusion fuel for DEMO?
• Fuel cleanup• Isotope separation• Tritium storage and delivery• Water detritiation• Tritium pumping• Effluent detritiation
Process
Glovebox
Air• Gas analysis• Process control
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1.1.2 What is needed to provide torus vacuum and fueling for DEMO?
• Torus Vacuum pumps • Roughing pumps• Gas puffing• Pellet fueling• Disruption mitigation• ELM pacing
Snail pump under test at LANL.
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1.1.3 What is needed to adequately contain and handle tritium for DEMO?
• Primary, secondary and tertiary containment
• Permeation barriers• Occupational and environmental
tritium monitoring• Maintenance systems• Waste handling, characterization and
processing• Decontamination and
decommissioning• Personnel protection equipment
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1.1.4 What is needed to adequately perform tritium accountability and nuclear facility operations for DEMO?
• Tritium accountability measurement techniques
• Tritium accountability methodology and procedures
• Non-Proliferation approaches• Systems and approaches to ensure
worker and public safety (authorization basis)
• Tritium transportation technology and approaches
• Waste repository• Tritium supply
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1.1.5 What is needed to breed tritium for DEMO?
• Tritium breeding blanket materials and configurations• Blanket structural materials• Blanket operations and control• Blanket maintenance and disposal• Blanket diagnostics
0.6 – 0.8 mm Li2TiO3 pebbles (CEA)0.2- 0.4 mm Li4SiO4 pebbles (FZK)
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1.1.6 What is needed to extract tritium from the breeding system for DEMO?
• Tritium extraction from breeding materials• Tritium extraction from blanket coolants• Tritium extraction diagnostics• Blanket systems tritium handling and containment
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1.1.7 What is needed to characterize, recover and handle in-vessel tritium for DEMO?
• In-vessel tritium characterization• In-vessel tritium control and removal• In-vessel component waste handling• Mitigation of in-vessel off-normal
effects on tritium systems
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Backdrop
State-of-the-art6 liters/minTime requirement 24 hr100 gm inventoryDuty cycle: 15%“Power”: 1000 MW
Need for ITER120 liters/minTime requirement 1 hr4000 gm inventoryDuty cycle: 5%Power: 400 MW
DEMO
Need for DEMO500 liters/min?Time requirement 1 hr6000 gm inventoryDuty cycle: 50%Power: 2000 MW
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1.1.1 Process Fusion Fuel
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State-of-the-Art
• Systems developed at TSTA, JAERI, FzK, JET, SRNL, TFTR, Chalk River and other facilities define the state-of-the-art. These systems were typically tested at 1/20th scale (or less) of ITER.
• ITER will be a major technological challenge and much will be learned from ITER. The ITER tritium systems will largely be a production system with little opportunity for experimentation.
• DEMO will higher throughput (4x ITER) and duty factor (10x ITER)
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Gaps
• Fuel Cleanup: Technology improvement• Isotope Separation: Tritium inventory and technology improvement• Tritium Storage and Delivery: Technology and assaying
improvement• Water Detritiation: Technology improvement. Need low-level
tritiated water processing system.• Pumping: Need larger capacity pumps• Effluent Detritiation: Would benefit from system which does not
produce water• Gas Analysis: Technology improvement• Process Control: Duty cycle and flowrate will require better control• Modeling: Accurate, easy-to-use models will be essential
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1.2 Provide vacuum and fueling
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Torus Vacuum Pumping
• Function: The torus vacuum pumping must maintain low divertor pressure (~10 Pa) while removing helium ash that will be generated by the fusion burn.
• State-of-the-art: The pumping system for ITER consists of 8 cryosorption pumps that are regenerated every 5 minutes in a cyclic fashion. These pumps are backed by tritium compatible roughing pumps (still under development). Frequent regeneration will be challenging.
• DEMO requirements: 4x ITER on flowrate and 10x on duty cycle.
• Gaps: Roughing pumps and torus cryopumps. Pumps that separate species have advantages.
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Fueling
• Function: The fueling system must provide DT fuel to the burning plasma and also provide gas to the SOL and divertor to minimize impurity generation and sweep impurities to the divertor.
• State-of-the-art: The pellet fueling system for ITER will be the state-of-the art.
• DEMO requirements: 4x ITER on flowrate and 10x on duty cycle. Pellet penetration requirement may be increased.
• Gaps: TBD based on fueling penetration requirements, feed rate, tokamak/not tokamak, etc.
22State-of-the-art pellet injector
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Disruption and ELM Mitigation
• Function: Provide massive gas injection(?) for disruption mitigation and rapid small pellets for ELM pacing
• State-of-the-art:
– For disruption mitigation gas jets.
– ELM mitigation with pellet pacing is not well developed at all. The next few years will hopefully answer the question of whether or not this could be employed.
• DEMO Requirements: The requirements for disruption and ELM mitigation in DEMO are completely unknown at this point. These requirements could have a significant effect on the fueling and pumping systems as well as the overall fuel cycle design.
• Gaps: TBD at this point
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1.1.3 Contain and handle tritium
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Tritium containment and handling
• State-of-the-art: Experience at recent tritium facilities. ITER will be challenged in this area.
• Demo requirement: Operation of high-temperature machine with useful power extraction and high duty factor.
• Gaps– Control of tritium through non-traditional equipment (heat
exchangers; large, high-temperature components; long high-temperature pipe runs)
– Primary, secondary and tertiary containment . Room processing systems.
– Permeation barrier would help (but development has not been successful, and the barrier factor degrades under irradiation)
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1.1.4 Tritium accountability and nuclear facility operations
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Tritium Accountability Measurements
• State-of-the-Art– Dedicated/custom calorimeters: ± 0.25% in 6-8 hours
– P-V-T-Composition tank measurements: 2% or less
– In-bed accountability: 1-2% of full bed inventory
• Demo Requirements– Accuracy of ± 2 grams T2 out of “kilograms being processed”
• Gaps– ITER “inventory-by-difference” errors propagate quickly. Direct
methods of “estimating” tritium inventory need to be developed .
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Tritium Accountability Methodology and Procedures. Non-Proliferation.
• State-of-the-Art– Periodic reconciliation between “book” inventory versus “physical”
inventory
– Attractiveness level defined by DOE Orders. Tritium is less attractive than special nuclear materials, but still requires safeguards
– “Gates, Guards, and Guns” with access restrictions
• Demo Requirements– Ensure no surreptitious diversion of tritium
• Gaps– Method to meet requirements (measurement or protection)
– Address political concerns
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Tritium Safety (Authorization Basis/Licensing)
• State-of-the-Art– DOE, NRC, Fusion Safety Code and ITER requirements
– Risk-based assessments used for calculation of dose to the public
– “Agreements” made between contractors and DOE for chronic emission limits from facilities
• Demo Function/Requirements– Some type of licensing/regulations will be required
• Gaps– Agreement to arbitrarily “low” emission requirements may be cost
prohibitive for Demo
– Permits required for discharge above drinking water standard
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Tritium Waste Disposal
• State-of-the-Art– (see Safety and Environmental presentation)
• Demo Function/Requirements– Some type of on-site or permitted disposal site will be needed
• Gaps– Assurance that fusion will not suffer from “Yucca Mountain
syndrome”
– Recycle option from “Safety and Environmental” presentation needs to include tritium recovery functionality in project scope
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1.1.5 Breed tritium
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Blanket HCPB (Solid Breeder) HCLL (Pb-17Li breeder)
Struct. material EUROFER EUROFER
Coolant He He
0per. pressure 8 MPa 8 MPa
T inlet-outlet 300-500°C 300-500°C
Breeder Pebble beds;Li4SiO4 [63% PF, 40% 6Li]Li2TiO3 [63% PF, 70% 6Li]
PbLi [90% 6Li]
Multiplier Pebble beds: Be [63% PF] -
Lifetime 7.5 MWa/m2 7.5 MWa/m2
T extraction from blanket
Low pressure (1bar)He purge loop
PbLi slowly re-circulatingat geodetic pressure
Operation mode Continuous (or altern. 1h-pulses)
Segmentation large modulesmax. dim. 2.0x2.0 m
Fusion / Electric Power 1800 / 750 MW
Net efficiency 40.5 %
Surface heating (av/peak) 0.4 / 0.5 MW/m2
Neutron wall load (av/peak) 2.0 / 2.4 MW/m2
EU DEMO Breeding Blankets Parameters
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Blanket systems are complex and have many integrated functions, materials, and interfaces
Tritium BreederLi2TiO3 (<2mm)
First Wall(RAFS, F82H)
Neutron MultiplierBe, Be12Ti (<2mm)
Surface Heat FluxNeutron Wall Load
[18-54] mm/s
PbLi flow scheme
[0.5-1.5] mm/sHCLL
HCSB
Solid Breeder Blanket utilizes immobile solid Solid Breeder Blanket utilizes immobile solid lithium ceramic breeder and Be multiplier for lithium ceramic breeder and Be multiplier for tritium self-sufficiencytritium self-sufficiency
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US DCLL Blanket The Dual Coolant Lead Lithium (DCLL) TBM Concept provides a pathway to high outlet temperature with RAFS and SiC Flow Channel Inserts (FCI) to thermally and electrically isolate PbLi breeder/coolant
PbLi Flow Channels
He-cooledFirst Wall
PbLi
He
He
SiC FCI
2 mm gap484 mm
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NGK Be-pebble
State-of-the-art R&D on solid breederState-of-the-art R&D on solid breeder
In-pile pebble bed assembly tests
Out-of-pile tests (ENEA)
Li4SiO4 pebbles in filling
NRG
Unit: mm
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Tritium breeding summary
• State-of-the-art: Multiple solid and liquid breed concepts. Parts of these concepts have been tested. No realistic, integrates tests have been performed.
• Demo requirement: Demo must breed all of its own tritium.• Gap: Integrated testing, demonstration and qualification of
Demo breeder needed prior to Demo construction– Example sub-gaps:
• For DCLL, what characterizes the flow channel inserts (FCI) made of SiCf/SiC composite for the dual coolant lead lithium (DCLL) blanket application, and how will such a component maintain its function throughout blanket lifetime?
• For solid breeder: What radiation resistant properties should the solid breeder pebble have in order to maintain good tritium release properties throughout blanket lifetime?
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1.1.6 Recovery of bred tritium
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Bred tritium extraction summary
• State-of-the-art: Data-to-date suggest that tritium recovery from the breeding material with acceptable tritium inventory is feasible. However, only preliminary tests have been performed.
• Demo requirement: Recover tritium so that inventory and tritium migration is acceptable
• Gap:– Select and test tritium extraction methods
– Demonstrate that tritium can be reduced to levels which will not challenge containment systems. Include extraction from Be.
– Testing in concert with 14 MeV neutrons, high burn up and high flux are needed.
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1.1.7 Characterize, recover and handle in-vessel tritium
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In-Vessel Tritium Holdup – Function & State-of-Art
• State-of-the-Art
– Full W and/or Be wall test planned on JET and Asdex-Ug
– ITER design includes C (strike point) and W for divertor, and Be wall
– Data from deuterium-fueled toroidal and linear experiments indicate difficulties for using C and Be in Demo (erosion, co-deposition, migration etc.)
– Infiltration and damage by He in W plasma facing component observed under non-Demo-like environment
• Demo Function/Requirements
– Relatively low burn fraction results in high fueling rates
– Presently assume W PFC and first walls with only limited erosion, re-deposition, and co-deposition.
– Will have much higher temperature than ITER
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In-Vessel Tritium Holdup – Gaps & Research Thrust
• Gaps– Presently there is no W PFC testing data in Demo-like nuclear
environment
– Tritium hold-up issues can be drastically reduced if (burn up fraction) / (recycling coefficient) could be substantially reduced
• Needed Research– Test Tritium Hold-up on W divertor and First Wall under Demo-
relevant conditions
– Test and develop knowledge needed to increase (burn up fraction) / (recycling coefficient) under relevant toroidal plasma conditions ( Themes I, II, III)
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Additional Issues
• Tritium recovery in waste components– ITER: high temperature bake out in tritium controlled hot cell
• Hold-up in hidden and cooler areas (gaps, ducts, behind in-vessel components such as RF launchers, etc.)– Maintain similar temperature in these components
• Wall conditioning produced tritium stream– ITER: use available tritium exhaust and recovery system
• Impurities introduced into vessel due to abnormal or accidental conditions including from auxiliary systems such as NBI (SF6 insulator)– Limit material choices for in-vessel and auxiliary systems
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Gap Summary
Area Gap
Fuel processing Major scale-up may require new/different technologies or approaches
Vac & FuelMajor scale-up may require new/different
technologies or approaches
T HandlingMajor scale-up may require new/different
technologies or approaches
Nuc FacMajor scale-up may require new/different
technologies or approaches
T BreedingMust develop and demonstrate Demo-
relevant technology
Extraction of bred T Must develop and demonstrate Demo-relevant technology
In-vessel TMust develop and demonstrate Demo-
relevant technology
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Fuel Processing Thrusts
• Tritium processing facility• CTF• Heated loop• ITER TBM• Neutron-irradiated permeation experiment• Tritium extraction from breeder• Modeling
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Thrust notes
• CTF and ITER TBM from a tritium standpoint will likely be “production” facilities and will afford little opportunity for experimentation
• The other thrusts will provide much opportunity for experimentation
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Initial ideas for fuel cycle thrusts
How do we close the fusion fuel cycle?
Area
Tritium Processing
Facility CTFHeated
Loop ITER TBM
Neut-irr Permeation
BarrierExtract. Exper. Modeling
Fuel processing xx xx X x x
Vac & Fuel xx xx x
T Handling x x Xx xx x x
Nuc Fac xx xx X X x
T Breeding Xx xx x
Extraction of bred T xx Xx xx xx x
In-vessel T x X X x x