Etude de l’incinération du plutonium en REP MOX sur support d’uranium enrichi avec le code de simulation dynamique du cycle CLASS

Abstract : Nuclear fuel cycle simulation codes are used to evaluate fuel cycle future strategies and understand the nuclear fuel cycle physics. In the context of uncertainty related to the future of French nuclear fleet, especially on theSodium Fast Reactor (SFR) deployment, the present work aims to study alternative solutions for plutonium and heavy isotopes management, based on Pressurized Water Reactor (PWR). Two hypothesis have been formulated to identify strategies. First, a delay has been expected in SFR deployment which induces a stabilization of plutonium inventory before SFR integration. The second hypothesis is based on the assumption that SFR won’t be deployed in France. For this specific case, a plutonium incineration strategy has been studied to quantify the PWR plutonium inventory reduction capacity. Fuel cycle simulations are performed using the fuel cycle simulator CLASS developed by the CNRS/IN2P3 in collaboration with IRSN. Plutonium multi-reprocessing in thermal reactor requires an innovative fuel. Developments have been made to simulate a fuel composed of MOX on enriched uranium support. An innovative methodology for fuel cycle simulation evaluation, based on Global Sensitivity Analysis, has been applied. This methodology leads to reference scenarios identification for plutonium and minor actinides inventories stabilization and reduction. Fuel cycle detailed simulations have been performed to produce fuel cycle data, to analyze PWR plutonium management at the cycle scale.
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Fanny Courtin. Etude de l’incinération du plutonium en REP MOX sur support d’uranium enrichi avec le code de simulation dynamique du cycle CLASS. Physique Nucléaire Expérimentale [nucl-ex]. Ecole nationale supérieure Mines-Télécom Atlantique, 2017. Français. ⟨NNT : 2017IMTA0044⟩. ⟨tel-01668610⟩

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