fusion-fission workshop september 30 – october 2, 2009...
TRANSCRIPT
Alternative Approaches
Fusion-Fission WorkshopSeptember 30 – October 2, 2009
Gaithersburg, Maryland
Albert MachielsSenior Technical Executive
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Topics
The Nuclear Fuel Cycle SimplifiedLight-Water Reactor (LWR) Power BlockManaged StorageFast Breeder Reactor (FBR) Power BlockGeologic Disposal
Conclusion/Discussion
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LWR Power Block
Managed Storage
Geologic Repository
FBR Power Block
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LWR Power Block: U-235 (0.711% of Unat) Energy
UsedUOX Storage
(Wet)
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Used LWR Fuel – Waste or Resource?
TRU
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“Managed Storage”
UsedUOX Storage
(Dry/Wet)
UsedUOX Storage(& UrepOX)(Dry/Wet)
URep
Used MOXStorage(Wet)
UOX Reprocessing
FPs & MAs(Glass)
UdeplMOX Fab
LWR-MOX
Pu
LLW/TRUDisposal
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Decay Heat from Used UOX Assemblies
Decay Heat of Spent UOX (W/tHM) as a function of time after irradiation
0
200
400
600
800
1000
1200
1400
1600
1800
2000
0 20 40 60 80 100 120 140 160
TotalActinidesPFPuAmCmSr+YCs+Ba
Source: EDF (July 2009)
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Decay Heat from Used MOX Assemblies
Decay Heat of Spent MOX (W/tHM) as a function of time after irradiation
0
1000
2000
3000
4000
5000
6000
0 20 40 60 80 100 120 140 160
TotalActinidesPFPuAmCmSr+YCs+Ba
Source: EDF (July 2009)
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“Managed Storage”“Open Fuel Cycles”
HLWRepository
“Closing the Fuel Cycles”
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“Closed Fuel Cycles”FBR Power Block: U-238 (99.28% of Unat) Energy
FPs & MAsFPs MAs
HLWRepository
HLWRepository/Boreholes
MOX Reprocessing
MOX (& Blanket) Fab
FBR
Udepl
Pu
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International Developments
• Russian Federation– BN-600 [1470 MWth]: operating since April 1980– BN-800: under construction with planned start-up in 2016
• China– China Experimental Reactor (CEFR) [65 MWth]: first
criticality planned in 2009• Japan
– Monju reactor: shutdown since 1995 following sodium leak
– Expected to re-start by the end of March 2010• India
– 500-MWe Prototype Fast Breeder Reactor (PFBR): under construction at Kalpakkam
– First criticality by the end of 2010
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International Developments (continued)
• France– Two designs: Helium- &
Sodium-cooled fast reactors– Progress report due Fall ’09– Preliminary design due in
‘12– Detailed design due in ‘15– Operating prototype in ‘20– Planned introduction of first
unit in EDF fleet: during ’40-’50 decade
Generation 3
Generation 4Present Fleetlifetime 40 yrs
Present Fleetover 40 yrs
0
10000
20000
30000
40000
50000
60000
70000
1975
1980
1985
1990
1995
2000
2005
2010
2015
2020
2025
2030
2035
2040
2045
2050
2055
2060
average lifetime of the fleet : 48 years
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Geologic Disposal
• Visible progress: Finland, Sweden, and France• Technical issues: not the dominating factors
– Societal acceptability and political stability (continuity of decisions) dominate!
– 1996 NAS Report:“No evidence that applications of advanced S&T have sufficient benefit for the U.S. HLW program to delay the development of the first repository for commercial spent fuel”
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Cooperation with EDF R&D – Nuclear Fuel Cycle Simulation Tools
0
10
20
30
40
50
60
70
80
90
100
110
1965 1980 1995 2010 2025 2040 2055 2070 2085 2100 2115 2130 2145
Year
Gen. II PWR Gen. III PWR CAPRA
Existing FleetALWRs
Fast Burner Reactors
“Burner” Scenario: Assume constant 100 GWe
• After 55 years of operation, existing reactors are first replaced by ALWRs
• When capacity of ALWRs reaches 65 GWe, existing reactors are then replaced by fast burners reactors with a conversion ratio of 0.5 (or CR = 0.5)
Once-through
“Burner” Scenario
From ~2040 on:
• “Once-through” fuel cycle continues build-up of spent fuel ( repository)
• “Burner” scenario results in a stabilization of the TRU inventory that is continuously recycled
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Time Required to Achieve TRU Inventory Reductions
8 23 70211
632
1334
0
200400
600
800
10001200
1400
1600
10% 25% 50% 75% 90% 95%
TRU Inventory Reduction (%)
Dep
loym
ent P
erio
d to
Ach
ieve
In
vent
ory
Red
cutio
n (y
ears
)
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LWR Power Block
Managed Storage
Geologic Repository
FBR Power Block
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Conclusion/Discussion
• LWR Power Block– Commercial operation
• Managed Storage– Commercial operation
• Geologic Disposal– Visible progress: Finland (spent fuel), Sweden (spent
fuel), and France (HLW glass canisters)
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Conclusion/Discussion (continued)
• Advanced Technologies (“FBR Power Block”)– Fast Reactors
• Some experience, but inconsistent performance• Key: economic competitiveness, assuming
continuity in present, re-invigorated RD&D programs
– Alternative: Accelerator-Driven Systems (ADS)• Key: demonstrate technical feasibility
– Reprocessing: long technological maturation• Reference: PUREX
– Manufacturing/Handling/Transportation• Costs and constraints associated with plutonium-
and minor-actinide-bearing fuels
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Conclusion/Discussion (continued)
• The primary goal is production of electricity– Economics will remain the main driver
• Cost of doing business includes safety and security• Complete advanced fuel cycle (fast reactor, reprocessing,
fuel fabrication) may be possible by mid-century– Issue: Industry engagement (French model)
• The true competition – Advanced Light Water Reactors– Proven reliability– Reduced concern about U availability– Probable success with implementation of spent
fuel/HLW disposal in some countries– Accepted regime for ensuring low proliferation risks