Optimization of a Calculation Scheme for the Treatment of Plutonium Recycling in Pressurized Water Reactors

Fougeras, Philippe; Cathalau, S.; Mondot, Jacques; Klenov, Pavel

doi:10.13182/nse121-32

Cited by 3 publications

(1 citation statement)

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“…In the EOLE facility, integral experiments with MOX fuel [42] started in 1984 with the ERASME program devoted to High-Conversion LWRs (under-moderated MOX lattices) [28]. These HCLWR studies were followed in 1989 by the EPICURE 30% MOX recycling program in standard PWR [29,30]. The MISTRAL programs (MISTRAL-2, MISTRAL-3 and MISTRAL-4), devoted to 100% MOX recycling in advanced PWR, were undertaken between 1997 to 2000 [31][32][33][34][35][36][37][38][39][40].…”

Section: Integral Benchmarksmentioning

confidence: 99%

Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

Noguère

Bernard

Blaise

et al. 2016

Nuclear Science and Engineering

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An overestimation of the k eff values for MOX fuels was identified with Monte-Carlo (TRIPOLI4) and deterministic (APOLLO2) calculations based on the Evaluated Nuclear Data Library JEFF. The overestimation becomes sizeable with the Pu-ageing, reaching a reactivity change of ∆ρ ≃ +700 pcm for integral measurements carried out with MOX fuel containing a large amount of Americium. This bias was observed on various critical configurations performed in the zero power reactor EOLE of the CEA Cadarache, France. The present work focuses on the improvements achieved with the new 239 Pu and 241 Am Evaluated Nuclear Data Files available in the latest version of the JEFF library (JEFF-3.2). The Resolved Resonance Range of the plutonium evaluation was re-evaluated at ORNL (Oak Ridge National Laboratory) with the SAMMY code in collaboration with the CEA Cadarache. The resonance parameters of the Americium evaluation were obtained with the REFIT code in collaboration with the research institutes IRMM

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Section: Integral Benchmarksmentioning

confidence: 99%