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AER working group F meeting Liblice, Czech republic April 14-17, 2009. Advanced Th fuel variations in VVER. Juraj BREZA 1,2 , Petr DAŘÍLEK 1 , Peter Čudrnák 2 , Vladimír NEČAS 2 breza@vuje.sk, darilek@vuje.sk, vladimir.necas@stuba.sk. 1 VUJE Inc., Okružná 5, 91864 Trnava, Slovakia
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AER working group F meetingLiblice, Czech republicApril 14-17, 2009 Advanced Th fuel variations in VVER Juraj BREZA1,2, Petr DAŘÍLEK1, Peter Čudrnák2, Vladimír NEČAS2breza@vuje.sk, darilek@vuje.sk, vladimir.necas@stuba.sk 1VUJE Inc., Okružná 5, 91864 Trnava, Slovakia 2Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Ilkovičova 3, 81219 Bratislava, Slovakia VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
MOTIVATION • Study of thorium cycles and its application on VVER-440 reactor • Decrease of plutonium production, plutonium transmutation VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
SCENARIOS Pu-Th mixed oxide fuel cycle (VVER-440) ThOX Pu - all isotopes 9.74 wt% Pu (5.40 wt% Pu-239) STORAGE PuThOXFabrication VVER-440(PuThOX core) Reprocessing UOX U 1.24 wt% Pu FPMA0.1% Pu0.1% U UOXFabrication VVER-440(UOX core) URT 4.2 wt% U-235 PuThOX Waste Enriched U VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
SCENARIOS U-Pu-Th mixed oxide fuel cycle ThOX Pu - all isotopes U - all isotopes UPuThOXFabrication VVER-440(UPuThOX core) STORAGE Reprocessing (U,Pu,Th)OX FPMAPu0.1% U UOXFabrication VVER-440(UOX core) Wastes URT 4.2% U-235 FPMA0.1% Pu0.1% U U UOX Reprocessing VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
COMPUTATION MODELS Model of homogeneousVVER-440 assembly Model of advancedComposite VVER-440 Assembly - MoCA VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
SCENARIOS VVERT fuel cycle The uranium was added to blanket because natural thorium does not includea fissile component, enriched uranium is required to provide a reasonable power density in the blanketduring the initial periodof U-233 buildup VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
INPUT DATA target burnup: core cycle:50 GWd/tHM 320 fpd, 5 years VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
RESULTS Potencial of Pu transmutation seed 4.2% U-235 seed 7.0% U-235 VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
RESULTS MA content in the fuel (g/tHM) VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
CONCLUSIONS • UPuThOX equilibrium cycle offers highest Pu transmutation ratio from selected scenarios • Composite assembly with Th fuel in the blanketdo not offer better plutonium generation rate asany of all selected fuel scenarios;it brings only lowest MA production per produced energy VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia
Thank you for your attention VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia