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Thorium Fuel Cycle Under VVER and PWR Conditions

17 th Atomic Energy Research Symposium Yalta, Crimea, Ukraine 24-28 September 2007. Thorium Fuel Cycle Under VVER and PWR Conditions. Juraj BREZA 1,2 , Petr DAŘÍLEK 2 , Vladimír NEČAS 1 breza@vuje.sk, darilek@vuje.sk, vladimir.necas@stuba.sk. 1 VUJE Inc., Okružná 5, 91864 Trnava, Slovakia

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Thorium Fuel Cycle Under VVER and PWR Conditions

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  1. 17th Atomic Energy Research SymposiumYalta, Crimea, Ukraine24-28 September 2007 Thorium Fuel Cycle Under VVER and PWR Conditions Juraj BREZA1,2, Petr DAŘÍLEK2, Vladimír NEČAS1breza@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

  2. CONTENTS • Motivation • Thorium fuel scenario • Results • Conclusions VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  3. MOTIVATION • Study of thorium fuel cycle and its application on VVER-440 and PWR reactor • Plutonium transmutation under light water reactor conditions • Participation in project RED-IMPACT focused on advanced fuel cycles VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  4. SCENARIOS UOX Open fuel cycle STORAGE UOXFabrication VVER-440(UOX core) FinalDisposal 4.2 wt% U-235 Enriched U VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  5. SCENARIOS Pu-Th MOX 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

  6. COMPUTATION MODELS Model of VVER-440 assembly Model of PWR assembly VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  7. INPUT DATA target burnup:50 GWd/tHM core cycle:320 days, 5 years Pu content estimation for VVER-440 thorium cycle Pu content estimation for PWR thorium cycle VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  8. RESULTS VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  9. CONCLUSIONS • Both investigated reactors fully loaded with thorium-plutonium fuel can transmute about 46 kg of Pu/tHM but PWR has a better efficiency • Introduction of an advanced fuel cyclein light water reactors does not solve the problemof plutonium burning;it only allows producing less of plutonium than it is produced today with classical UOX fuel • In the case of non-equilibrium cycles, where plutonium will be obtained from the stock of spent fuel, thorium fuel allows to burn Pu into approx. 50% of today store VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

  10. Thank you for your attention VUJE , Inc., Okružná 5, 918 64 Trnava, Slovakia; FEI STU, Ilkovičova 3, 81219 Bratislava, Slovakia

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