Study on SUPEL Scenario for Direct Recycling of Spent BWR Fuel in BWR
System
Abdul WARIS*, Sumbono, Indarta Kuncoro AJI, Novitrian, and Zaki SU’UD
Nuclear Physics & Biophysics Research Division,
Department of Physics, Institut Teknologi Bandung, Indonesia
Outline
Background
Objective
Methodology
Results and Discussion
Conclusion
PHYSI S
Background
Nuclear Energy Industry grows with 3 main issues:
1.
Reactor safety Multi-barrier System : Defense in Depth
2.
Nuclear Proliferation political aspects
3.
High level wastes (HLW) management
The truly problem in nuclear energy if we can manage HLW, public
acceptance maybe increase
Background …
Once countries decide to “go
nuclear” they may think about “HLW repository site” or at least
“underground research laboratory
(URL)”
PHYSI S
Underground Research Laboratories
130 Level
240 Level
300 Level
420 Level
VILKSISOv7 DIF10
DIF8 DIF9
DIF12 DIF13
Room 421 Room 301
Room 214
Room 413
DIF14 DIF7 DIF5DIF6
Generic URL: Kolar Gold Field, India
Site specific URL:Lac de Bonnet, Canada
(http://www.oecd-nea.org)
CMAME 2014
Background …
The other option they may choose
“closed cycle strategy” to recycle HLW in any type of nuclear reactor or hybrid
systems reprocessing plant is required
Its very difficult to have country’s own reprocessing plant International
regulation and very high cost
Even OECD countries likes Korea is not
allowed to has a reprocessing plant
PHYSI S
Background…
Spent Fuel Reprocessing
(http://www.jaea.go.jp/english/04/tokai-cycle/02.htm)
Background …
IAEA (International Atomic Energy Agency) suggests to construct and operate some
regional reprocessing plants (for example in east asia region)
Non-proliferation strategy proposed not to separate Plutonium with Minor Actinides during the spent fuel reprocessing
Some countries (especially which not
allowed to have any reprocessing plant
and enrichment plant) should find a best
way to deal with their HLW.
PHYSI S
DUPIC: Direct Use of spent PWR fuel In CANDU reactors Strategy
CANDU
Spent LWR/DUPIC Fuel PWR
Spent LWR Fuel
Uranium Saving
No
Disposal Less
Disposal
DUPIC
PWR once-through DUPIC Fuel Fab On-site Storage
Natural Uranium
AFR Storage
Permanent Disposal
On-site Storage
Permanent Disposal
* DUPIC : Direct Use of spent PWR fuel In CANDU reactors
Korea:
-Advanced NE Industry
-- Good budget
--Not allowed to have RP &
EP
-- More than 1 type of NPP (LWR
& CANDU)
Background …
Country likes Indonesia (not allowed to has reprocessing plant & enrichment plant, and If “go nuclear” may has only 1 type of nuclear reactor) should has another
alternative way for dealing with nuclear waste
Best nuclear power plant (NPP) candidate for Indonesia is LWR (light water reactor) either pressurized water reactor (PWR) or boiling water reactor (BWR)
We have proposed a scenario that called: SUPEL
(Straight Utilization of sPEnt LWR fuel in LWR reactors) scenario for Nuclear Waste Recycling Strategy
PHYSI S
SUPEL Scenario for Recycling Strategy
LWR
Spent LWR/SUPEL Fuel LWR
Spent LWR Fuel
Uranium Saving
No
Disposal Less
Disposal
SUPEL
PWR once-through SUPEL Fuel Fab On-site Storage
Enriched Uranium
AFR Storage
Permanent Disposal
On-site Storage
Permanent Disposal
* SUPEL : Straight Utilization of sPEnt LWR fuel in LWR reactors
Objective
We have evaluated SUPEL scenario for Nuclear Waste Recycling Strategy in PWR
The objective of this study is to evaluate the SUPEL scenario for BWR spent fuel direct recycling scheme in BWR System
PHYSI S
Methodology
Thermal power output 3000 MWth
Average cell power density 59 Wcm-3
Fuel pellet diameter 0.529 cm
Fuel rod diameter 0.615 cm
Pin pitch 1.444 cm
Fuel type Oxide
Cladding Zircaloy-2
Coolant H2O
Design parameter of studied BWR
Nuclear Power Plant using
Boiling Water Reactor (BWR)
PHYSI S
RESULTS and DISCUSSION
CMAME 2014
Effective multiplication factor (k-eff) of 3.0% of UO2 enrichment
BWR can not attain its criticality condition
0.85 0.9 0.95 1 1.05 1.1 1.15
5% Spent fuel 7% Spent fuel 9% Spent fuel 11% Spent fuel 13% Spent fuel 15% Spent fuel 17% Spent fuel 19% Spent fuel
Effective multiplication factor (k-eff)
PHYSI S
Effective multiplication factor (k-eff) of 5.0% of UO2 enrichment
BWR can attain its criticality condition for 5% enrichment
with 5% - 9%
spent fuel
0.9 0.95 1 1.05 1.1 1.15 1.2
0 200 400 600 800 1000 1200
5% Spent fuel 7% Spent fuel 9% Spent fuel 11% Spent fuel 13% Spent fuel 15% Spent fuel 17% Spent fuel 19% Spent fuel
Effective multiplication factor (k-eff)
Operation time (days)
Comparison of neutron spectrum
the neutron spectra become
harder (shifts to the high energy region) with the
escalating of trans-uranium (TRU) nuclides
in the reactor.
0 1 2 3 4 5
0.01 1 100 104 106
5% SF 7% SF 9% SF 11% SF 13% SF 15% SF 17% SF 19% SF
Relative Flux per unit lethargy
PHYSI S
Conclusion
The study on direct recycling of BWR spent fuel to support SUPEL scenario has been conducted.
The reactor can achieve it criticality for U-235 enrichment in loaded fresh fuel is higher than 5% with the amount of spent fuel in the core is less than 9%.
The neutron spectra become harder with the increasing of U-235 enrichment in loaded fresh fuel as well as the amount of spent fuel in the core.
