safety analysis of direct recycling of nuclear spent fuel ... · fuel pellet diameter 8.0 mm fuel...
TRANSCRIPT
Safety Analysis of Direct Recycling of
Nuclear Spent Fuel in
Light Water Reactor (LWR)
Abdul Waris, Indarta Kuncoro Aji,
Novitrian, and Zaki Su’ud
Asahi Glass 2012
Novitrian, and Zaki Su’ud
Nuclear Physics and Biophysics Research Division, Department of Physics,
Faculty of Mathematics and Natural Sciences,Institut Teknologi Bandung,
Jl. Ganesa 10 Bandung 40132, INDONESIA
Outline
� Background
� Objective
� Methodology
� Results and Discussion
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
� Results and Discussion
� Conclusion
Background
Nuclear Energy Industry grows with 3 main issues:
� Reactor safety: Multi-barrier System :
Defence at Depth
� Nuclear Proliferation: political aspects
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� Nuclear Proliferation: political aspects
� High level wastes (HLW) management
� The truly problem in nuclear energy
if we can manage HLW, public acceptance will increase
Background …
�Once countries decide to “go
nuclear” they may think about “HLW
repository site” or at least
“underground research laboratory
(URL)”
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(URL)”
Underground Research Laboratories
130 Level
Room 214
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240 Level
300 Level
420 Level
VILKSISOv7
DIF10DIF8
DIF9
DIF12
DIF13
Room 421
Room 301
Room 413
DIF14
DIF7DIF6DIF5
Generic URL : Kolar Gold Field, India
Site specific URL:Lac de Bonnet ,Canada,
Background …
� They may to choose “closed cycle
strategy” to recycle HLW in any type
reactor or hybrid systems (including
ADS(accelerator driven system))
�reprocessing plant is required
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
�reprocessing plant is required
� Its very difficult to have country’s own
reprocessing plant, besides it is very
expensive.
� Even OECD countries likes Korea is not
allowed to has a reprocessing plant
The Nuclear Fuel CycleUraniumMining
UraniumconcentrateYellow Cake
Conversion to UO 2 or UF6
Waste
Recovered Uraniumand Plutonium
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235U enrichment and Fuel fabrication
Nuclear Power Station – Electricity Generation
Used FuelStorage
Reprocessing and Recycling
Background …
� IAEA suggests to construct and operate some regional reprocessing plant (for example in east asia region)
� Non-proliferation strategy proposed not toseparate Plutonium with Minor Actinidesduring the spent fuel reprocessing
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
separate Plutonium with Minor Actinidesduring the spent fuel reprocessing
� Some countries (especially which notallowed to have any reprocessing plantand enrichment plant) should find a bestway to deal with their HLW.
DUPIC: Direct Use of spent PWR fuel In CANDU
reactors Strategy
CANDU
PWR
Spent LWR Fuel
Uranium Saving
DUPIC Fuel Fab
On-site Storage
Natural Uranium
Korea:
-Advanced NE Industry
-- Good budget
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Spent LWR/DUPIC Fuel
No Disposal
Less Disposal
DUPIC
PWR once-through
DUPIC Fuel FabAFR Storage
Permanent Disposal
On-site Storage
Permanent Disposal
* DUPIC : Direct Use of spent P WR fuel I n CANDU reactors
budget
--Not allowed to have RP &
EP
-- More than 1 type of
NPP (LWR & CANDU)
Background …
� Country likes Indonesia (no NE Industry,
less committed, limited budget, not
allowed to have RP & EP, If “go nuclear”
might have only 1 type of NPP) should has
another alternative way � SUPEL: Straight
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
another alternative way � SUPEL: Straight
Utilization of sPEnt LWR fuel in LWR reactorsscenario for Nuclear Waste Recycling Strategy
� Best NPP candidate for Indonesia either PWR or
BWR.
SUPEL Scenario for Recycling Strategy
LWR
PWR
Spent LWR Fuel
Uranium Saving
SUPEL Fuel Fab
On-site Storage
Enriched Uranium
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
Spent LWR/SUPEL Fuel
No Disposal
Less Disposal
SUPEL
PWR once-through
SUPEL Fuel FabAFR Storage
Permanent Disposal
On-site Storage
Permanent Disposal
* SUPEL : Straight U tilization of sPE nt LWR fuel in L WR reactors
Objective
� In our previous study on SUPEL PWR, we found
that the reactor can achieve it criticality when
the U-235 enrichment in loaded fresh fuel is ≥ 4%
and the amount of spent fuel in the core is ≤ 20%.
However, the safety aspect is not evaluated yet.
In the present report, we have performed a
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
� In the present report, we have performed a
safety analysis of direct recycling of spent PWR
fuel in PWR system, by evaluating the influence
of changing moderator-to-fuel volume ratio (MFR)
of PWR.
Methodology
Thermal power output 3000 MWth
Average cell power density 100 Wcm-3
Fuel pellet diameter 8.0 mm
Fuelroddiameter 9.6 mm
Design parameter of studied PWR
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Fuelroddiameter 9.6 mm
Pin pitch 11.8 mm
Fuel type Oxide
Cladding Zircaloy-4
Coolant H2O
Moderator-to-fuel volume ratio (MFR) 0.5 – 4.0
Nuclear Power Plant using Pressurized Water Reactor (PWR)
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Diagram of SUPEL Scenario
Methodology …
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Effective multiplication factor (k-eff) of 6.0% UO2
enrichment
1.05
1.1
1.15
1.2
MFR=0.5
MFR=1.0
MFR=1.5
MFR=2.0
MFR=3.0
MFR=4.0
Effe
ctiv
e m
ulti
plic
atio
n fa
ctor
(k-
eff) PWR can not
attain its criticality condition
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
0.85
0.9
0.95
1
1.05
0 200 400 600 800 1000 1200 1400
Effe
ctiv
e m
ulti
plic
atio
n fa
ctor
(k-
eff)
Operation time (days)
condition
Effective multiplication factor (k-eff) of 6.5% UO2
enrichment
1.05
1.1
1.15
1.2
MFR=0.5
MFR=1.0
MFR=1.5
MFR=2.0
MFR=3.0
MFR=4.0
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-ef
f) PWR can attain its criticality condition for
MFR = 4.0, since k-eff > 1 after more
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
0.85
0.9
0.95
1
0 200 400 600 800 1000 1200 1400
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-ef
f)
Operation time (days)
k-eff > 1 after more than 2/3 of operation time (cycle length)
Effective multiplication factor (k-eff) of 7.0% UO2
enrichment
PWR can attain its criticality condition for all MFR values, since k-eff > 1 after more
1.1
1.15
1.2
1.25
MFR=0.5
MFR=1.0
MFR=1.5
MFR=2.0
MFR=3.0
MFR=4.0
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-ef
f)
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
k-eff > 1 after more than 2/3 of operation time (cycle length)
0.85
0.9
0.95
1
1.05
0 200 400 600 800 1000 1200 1400
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-ef
f)
Operation time (days)
Effective multiplication factor (k-eff) of 7.5% UO2
enrichment
1. PWR can attain its criticality condition for All MFR
values, since k-eff > 1 during the whole
operation time (cycle length).2. The criticality can be achieved easier as the
increasing of MFR
1.15
1.2
1.25
MFR=0.5
MFR=1.0
MFR=1.5
MFR=2.0
MFR=3.0
MFR=4.0
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-e
ff)
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increasing of MFR
0.95
1
1.05
1.1
0 200 400 600 800 1000 1200 1400
Effe
ctiv
e m
ultip
licat
ion
fact
or (
k-e
ff)
Operation time (days)
Since in PWR, the moderator is also the coolant material,
more coolant means that cooling process becomes
faster. As a consequence, the safety of the reactor becomes
higher
Number density of actinides for 8.0% enrichment
for MFR=4.0
18
1020
1022
Nuc
lide
num
ber
dens
ity in
rea
ctor
(#/
cc)
The number density of Pu-239, Pu-240, Pu-241, and Cm-244 significantly reduce with the
augmenting of MFR.
In contrast, the number density
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1012
1014
1016
1018
0 200 400 600 800 1000 1200 1400
U-235U-238Np-237Pu-238
Pu-239Pu-240Pu-241Pu-242
Am-241Am-243Cm-242Cm-244
Nuc
lide
num
ber
dens
ity in
rea
ctor
(#/
cc)
Operation time (days)
In contrast, the number density of Pu-238, Am-241, Am-243,
and Cm-242 increase with the enlarging of MFR.
Conversion ratio for 3.5% and 7.5% enrichment
0.85
0.9
0.95
1
Con
vers
ion
ratio
(#)
The conversion ratio decreases with the
increasing of MFR as well as the
increasing of UO
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0.6
0.65
0.7
0.75
0.8
0 1 2 3 4 5
CR_3.5% U235CR_7.5% U235
Con
vers
ion
ratio
(#)
MFR
increasing of UO2enrichment in loaded
fresh fuel.
Neutron Flux for 3.5% and 7.5% enrichment
The neutron flux decreases with the
increasing of MFR as well as the
increasing of UO3.5 1014
4 1014
4.5 1014
5 1014
Flux neutron_3.5% U-235 Flux neutron_7.5% U-235
Flu
x ne
utro
n (#
/cm
2/s)
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increasing of UO2enrichment in loaded
fresh fuel.
1 1014
1.5 1014
2 1014
2.5 1014
3 1014
0 1 2 3 4 5
Flu
x ne
utro
n (#
/cm
2/s)
MFR
Conclusion
� Preliminary study on safety analysis of direct
recycling of PWR spent fuel to support SUPEL
scenario has been carried out.
� The reactor can achieve it criticality for as a
minimum 6.5 a% of U-235 enrichment in the loaded
fresh fuel with the fraction of spent fuel in the core
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
fresh fuel with the fraction of spent fuel in the core
is 5.0 %.
� The criticality can be achieved easier as the
increasing of MFR. Since in PWR, the moderator is
also the coolant material, more coolant means that
cooling process becomes faster. As a consequence,
the safety of the reactor becomes higher.
Arigatou Gozaimasu
Terima kasih
Asahi Glass 2012 | Institut Teknologi BandungPHYSI S
Terima kasih
Thank you