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)


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


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


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


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


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


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


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


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

All Rights Reserved. Copyright © 2010, Hitachi-GE Nuclear Energy, Ltd. 10

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


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


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


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


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


13


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


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


U Recovery Technology

CrystallizationCrystallizationCrystallizationCrystallization

Residue (Pu/FP/MA/U)

Recovered Recovered UU


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



Spent fue lSpent fue l

UF6 gas

Purification

F2

Fluorination (Flame reactor)

Solvent extractionSolvent extraction

Residue (U, Pu, MA&FP)



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


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


- 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

lwr spent fuel management for the smooth deployment of fbr

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