LWR Spent Fuel Management for the Smooth Deployment of FBR
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Transcript of LWR Spent Fuel Management for the Smooth Deployment of FBR
All Rights Reserved. Copyright © 2009, Hitachi-GE Nuclear Energy, Ltd.
LWR Spent Fuel Management for LWR Spent Fuel Management for the Smooth Deployment of FBRthe Smooth Deployment of FBR
ICSFM (IAEA-CN-178) Paper 11-02 (Vienna, 2010.5.31 - 6.4)
T. Fukasawa1, J. Yamashita1, K. Hoshino1, A. Sasahira2, T. Inoue3, K. Minato4, and S. Sato5
1 Hitachi-GE Nuclear Energy, Ltd., 2 Hitachi, Ltd., 3 Central Research Institute of Electric Power Industry,
4 Japan Atomic Energy Agency, 5 Hokkaido University
2All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 2
Transition from LWR to FBR
Reprocessing reduces LWR-SF and supplies Pu (MOX) for FBR deployment. Reprocessing reduces LWR-SF and supplies Pu (MOX) for FBR deployment.
LWR LWR/FBR Fuel Reprocessings
FBRCycle
FBR
LWRCycle
Spent Fuel Storage
FuelFabrication
U Front End
FuelFabrication
ReactorDecommissioning
Operation WasteTreatment & Disposal
Reprocessing WasteTreatment & Disposal
Operation WasteTreatment & Disposal
L/F Transition(Pu supply)
3All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 3
According to the Japan’s Nuclear Energy Policy Framework published in 2005 by the Atomic Energy Commission, FBR will be deployed from around 2050 under its suitable conditions by the replacement of 60y old light water reactors (LWR).
The Framework mentioned that all spent fuels (SF) should be reprocessed (SF amounts reduction) and recovered Pu, U should be effectively utilized, while possessing no excess Pu.
Recovered Pu in Rokkasho Reprocessing Plant (RRP) will be utilized (consumed) in LWR-MOX.
Recovered Pu in the next reprocessing plant which will start operation around 2050 will be utilized for fast breeder reactors (FBR) deployment.
The next reprocessing plant(s) will treat SF from LWR-UO2, LWR- MOX and FBR.
Pu balance control by flexible fuel cycle system is quite important considering FBR deployment time and rate which are changeable.
Transition from LWR to FBR
4All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 4
Typical FBR Deployment Pattern
2000 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100 2110
[年度]
Existing LWRs(60y operation)
FBRs
New LWRs(60y operation)
Pla
nt
ca
pa
cit
y (G
We
)
Year
58GWe
0
10
20
30
40
50
60
70
5All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 5
Transition Fuel Cycle Systems
~90% ~90%
100 % 100 %
Pu,(MA),UPu,(MA),U
FBR cycleFBR cycle
FBR FBR FabricationFabrication
Recovered UF
BR
fue
lF
BR
fue
l
~90% ~90%
U recoveryU recovery 100 % 100 %
Recycle materialRecycle material
Pu,FP,MA,UPu,FP,MA,U
FBR cycleFBR cycle
FBR FBRFabricationFabrication
AA
BBTemporary
storageTemporary
storage
LW
R s
pe
nt
fue
l
Fabric.Fabric.
FF
CI s
yste
mF
FC
I sys
tem
Ref
. sys
tem
Ref
. sys
tem
Reproc.Reproc.
Recovered U
[2nd LWR reproc.]
[2nd LWR reproc.]
FBR reproc.FBR reproc.
A: Rapid FBR deploymentB: Slow FBR deployment
Extraction, Crystallization, Fluorination, etc.
LW
R s
pe
nt
fue
l
FB
R f
uel
FB
R f
uel
FB
R f
uel
FB
R f
uel
Two fuel cycle systems and several Pu balance control methods were investigated. If the FBR deployment rate decreases, Reference and Flexible Fuel Cycle Initiative (FFCI) systems will temporarily store LWR SF or FBR FF (Pu product) and recycle material (RM), respectively.
Two fuel cycle systems and several Pu balance control methods were investigated. If the FBR deployment rate decreases, Reference and Flexible Fuel Cycle Initiative (FFCI) systems will temporarily store LWR SF or FBR FF (Pu product) and recycle material (RM), respectively.
AA
BB BBTemporary storageTemporary storage
A: Rapid FBR deploymentB: Slow FBR deployment
FP,(MA) FP,(MA) FP,(MA) FP,(MA)
FP,(MA) FP,(MA)
FBR reproc.FBR reproc.
Low proliferation resistance
6All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 6
Temporary Storage Materials
Radiation dose from the storage material at 1m distance
RM: Recycle material (Pu/FP/MA/~10%U), SF: Spent fuel, FF: Fresh fuel, MA: Minor actinides
Equ
ival
ent
dose
rat
e @
1m
(re
m/h
)
Fatal level
105
50y cooling104
103
102
101
1
10-1
7All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 7
FBR startup
No limit / 30t Pu (20t Puf)
UO2 fuel (GWd/t): 33 (-2004), 45 (2005-2039), 60 (2040-)MOX fuel (GWd/t): 33 (-2024), 45 (2025-2039), 60 (2040-)
58GWeNuclear capacity
LWR capacity factor
Burn up of LWR-SF
Factor
80% (-2009), 85% (2010-2029), 90% (2030-)
FBR deployment rate
2040, 2060, 2090
FBR core design(Breeding ratio)
2050
Replace all LWR (60y) with FBR
70GWe
Replace ½ LWR, 1GWe/y constant, 2 step (1.5 - 0 - 1.5GWe/y)
Pu storage amount* 0t Pu
Excess Pu countermeasure
Storage of FBR-FF (Pu product) / LWR-SF, RM
FBR SF storage, FBR fresh fuel storage, Pu use in LWR
Oxide fuel high conversion core (1.13)
Oxide fuel compact core (1.10), Metal fuel (1.0)
1
2
3
4
5
6
7
8
RRP: 2008-, 2nd plant: 2048-, 3rd plant: 2088- ; or 2nd: 2048-2100LWR reprocessing
40y (LWR and FBR reprocessing plants)
>3y (LWR-SF), >4y (FBR-SF)SF cooling time
Reactor life 60y (LWR and FBR)
Reprocessing life
9
10
11
12
No Base case Variations
*30t Pu is same as RRP, Puf is fissile Pu (~2/3 Pu for LWR-SF)
Mass Balance Analysis
8All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 8
LWR-SF Amounts
10000
20000
30000
40000
50000
2000 2050 2100
Year
Cum
ula
tive
LW
R s
pen
t fu
el a
mou
nts
(t)
0
60000
70000
U removal;900t/y -> 1200t/y
10000
20000
30000
40000
50000
2000 2050 2100
Year
Cum
ula
tive
LW
R s
pen
t fu
el a
mou
nts
(t)
0
60000
70000RRP (800t/y) only
No reprocessing
2nd RRP (1200t/y)from 2050 to 2110
Reprocessing is effective to reduce LWR-SF. 2nd reprocessing plant is needed after RRP with higher capacity than that of RRP. Much higher capacity or 3rd reprocessing plant is needed to treat all LWR-SF. FBR deployment delay also necessitates the much higher capacity or 3rd reprocessing plant. FFCI can reduce LWR-SF more effectively than reference system.
Reference system FFCI system
FFCI
RM
9All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 9
LWR reprocessing Amounts
1650 t/y
0
500
1,000
1,500
2,000
2000 2050 2100 2150
UO2MOXRRP
650 t/y
1200 t/y
0
500
1,000
1,500
2,000
2000 2050 2100 2150
U rem ovalMOX reproc.RRP
LWR
rep
roce
ssin
g am
ount
(t/
y)
YearYear
Reference system FFCI system
LWR-MOX-SF with high Pu content is reprocessed at high FBR deployment rates.
Reference system needs 2nd and 3rd reprocessing plants (full function) of 1650 t/y capacities.
FFCI system needs 1200 t/y and 650 t/y capacities for 2nd and 3rd reprocessing plants (only uranium removal functions), respectively.
10
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FBR reprocessing AmountsF
BR
Rep
roce
ssin
g am
ount
(t/
y)
0
500
1,000
2000 2050 2100 2150
250 t/y255 t/y
250 t/y, 8 y
300 t/y, 7 y
0
500
1,000
2000 2050 2100 2150YearYear
Reference system FFCI system
FBR reprocessing capacity increase at around 2090 is reasonable for the transition period.
Reference system needs 250 t/y capacity at around 2055 and 255 t/y at around 2095.
FFCI system needs earlier construction of FBR reprocessing plants that must also supply initial Pu for FBR deployment, 250 t/y capacity at around 2047 and 300 t/y at around 2088.
11
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Pu Storage AmountsP
uf s
tora
ge a
mou
nt (
t)
0
50
100
150
200
2000 2050 2100 2150
Excess Puf (fissile Pu)
20 t
Puf in recycle material
132 t
0
50
100
150
200
2000 2050 2100 2150YearYear
Reference system FFCI system
Excess amount of Puf storage as reprocessing product is controlled below 20 t concerning the proliferation resistance.
Reference system with 20 t Puf storage limit affects the LWR-SF reprocessing amount.
FFCI system stores 132 t Puf (max.) in recycle material with high proliferation resistance, which does not affect the LWR-SF reprocessing amount.
12
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LWR-SF Storage AmountsLW
R-S
F s
tora
ge a
mou
nts
(ktH
M)
0102030405060
2000 2050 2100 2150
Total LWR SFLWR SF AFR (UO2+MOX)
01020304050
60
2000 2050 2100 2150
Total LWR SFLWR SF AFR (UO2+MOX)
2nd reprocessing plant with high capacity is needed after RRP to reduce LWR-SF.
Reference system shows the second storage amount peak at around 2090 and needs AFR (away from reactor) storage facility even after 2080.
FFCI system can reduce LWR-SF more effectively than reference system.
YearYear
Reference system FFCI system
13
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Cost Estimation Results
FFCI cost effect (%)*
10 20 30 40 50
*(Reference cost – FFCI cost)/Reference cost
FBR rate(GWe/y)
L SFMOX/HC58L-F2050
FBR pace
Pu Stor.
Fuel/Core
Total GWe
FBR start
No
MOX58L-F2050F SF58L-F2050F FF58L-F2050
M/HB58L-F2050MOX/C58L-F2050
70L-F2050
58L-F2090
58Const.2050582 step205058½L-F2050
58L-F2060
58L-F2050
58L-F204022
0.521
1.512222222
L SFL SFL SFL SFL SFL SFL SFL SFL SF
L SF
MOX/HCMOX/HCMOX/HCMOX/HCMOX/HCMOX/HCMOX/HC
MOX/HCMOX/HCMOX/HCMOX/HC
12345678
14131211109
No Pu limit30t Pu limit
0t Pu
14
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Conclusions
This study includes the results of “Research and Development of Flexible Fuel Cycle for the Smooth Introduction of FBR” entrusted to Hitachi-GE Nuclear Energy, Ltd. by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).
The transition scenarios from LWR to FBR and the correspond fuel cycle (reference and FFCI) systems are investigated. As a result, the FFCI system can reduce the LWR-SF reprocessing capacity, LWR-SF reprocessing function, low proliferation resistant Pu storage amount, LWR-SF interim storage amount, and the total fuel cycle cost.
The most unique and important issue to be solved for the FFCI system is safety of the RM storage. Heat transfer property and hypothetical criticality accident are analyzed by using the data obtained from the simulated RM oxides, which clarifies the enough safety for heat removal and criticality.
These investigations show the effectiveness of the FFCI system for the transition period fuel cycle from LWR to FBR.
15
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U Recovery Technology
CrystallizationCrystallizationCrystallizationCrystallization
Residue (Pu/FP/MA/U)
Recovered Recovered UU
Recycle materialRecycle material
UO2(NO3)2
crystalDissolvedsolution
Crystallization(Cooler)
Spent fuelSpent fuel
Micro waveDenitration
Fluoride volatilityFluoride volatility
Oxide conversion
UF6 gas
Residue (U, Pu, MA&FP) Steam, H2
Recovered Recovered UU
Recycle materialRecycle material
Spent fue lSpent fue l
UF6 gas
Purification
F2
Fluorination (Flame reactor)
Solvent extractionSolvent extraction
Residue (U, Pu, MA&FP)
Recovered Recovered UU
Recycle materialRecycle material
U solution
Dissolvedsolution
Spent fuelSpent fuel
Extraction(Pulsed column)
(Centrifugal contactor)
Denitration
-U recovery residues are nitrate solutions for solvent extraction and crystallization, and fluoride powder for fluoride volatility.
-Recycle material (RM) would be nitrate solution, nitrate powder, fluoride powder or oxide powder.
-Oxide powder is most stable and aqueous process is applied to reprocessing, thus simulated oxide RM was prepared from nitrate solution in this work.
16
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Preparation of Recycle Material
RM preparation method must consider easy treatment, safe storage, and compatibility with FBR reprocessing. RM preparation method must consider easy treatment, safe storage, and compatibility with FBR reprocessing.
Example of RM
preparation method
U recovery residueU recovery residue
DecontaminationCapping
Canister for RM storageCanister for RM storage
Calcinater (Rotary kiln)Calcinater (Rotary kiln)
HeaterHeater
[Ref.: AVM process]
Liquid→PowderLiquid→Powder
Diameter controlDiameter control
Filling
To storage
Dust removal
Recycle material (RM)Recycle material (RM)
17
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- Air cool, natural convection- Similar design to vitrified HLW storage facility- Criticality safety by the Pu amount limitation, etc.
- Air cool, natural convection- Similar design to vitrified HLW storage facility- Criticality safety by the Pu amount limitation, etc.
Recycle M.(estimated)
5. Pu conc. (wt%) ~15 0
1. Component
6. After-treatment
FP,MA, Pu,U
Reprocessing Disposal
Vitrified HLW
4. Heat (W/cc)
3. Density (g/cc)
Lump
ItemMater.
~0.010.01-0.04
FP,MA,B-Si glass
1-3
2. Form Granule
2.7
Specification
Storage areaStorage area
30CAir
Recycle material Recycle material storage facility (ex.)storage facility (ex.)
Cooling air
Floor crane
Bottom supportBottom support
Support
Ceiling slabCeiling slab Containment lid
Air pipe
Containment pipe
Canister
Recycle material
Cooling air
Canister
Vitrified HLW
~450D>150D
Storage of Recycle Material
Cooling air
Canister