MACROS Benchmark Calculations And Analysis Of Fission Gas Release In MOX With High Content Of Plutonium

Sergei Lemehov; Frédéric Jutier; Yves Parthoens; Benedict Vos; Sven Van den Berghe; Marc Verwerft; N. Nakae

doi:10.1016/j.pnucene.2011.12.010

MACROS Benchmark Calculations And Analysis Of Fission Gas Release In MOX With High Content Of Plutonium

Sergei Lemehov, Frédéric Jutier, Yves Parthoens, Benedict Vos, Sven Van den Berghe, Marc Verwerft, N. Nakae

Research output › peer-review

Abstract

This paper focuses on the modelling of fission gas release in mixed oxide fuel. In a first part, the irradiation experiment, conducted by the Japanese Nuclear Energy Safety organization on high enriched mixed oxide fuel, is outlined. In a second part, the approach for fission gas release modelling, as implemented in the fuel performance code MACROS, is explained and a comparison between calculated and experimental results is made. The code MACROS is conceived to provide not only integral (rod average) results on fission product and fission gas retention and release, but also to calculate local concentrations (radial profiles). In this way, it is possible to compare results from post-irradiation examinations with calculated profiles.

Original language	English
Pages (from-to)	117-124
Journal	Progress in Nuclear Energy
Volume	57
DOIs	https://doi.org/10.1016/j.pnucene.2011.12.010
State	Published - 6 Mar 2012

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10.1016/j.pnucene.2011.12.010License: Other

Cite this

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title = "MACROS Benchmark Calculations And Analysis Of Fission Gas Release In MOX With High Content Of Plutonium",

abstract = "This paper focuses on the modelling of fission gas release in mixed oxide fuel. In a first part, the irradiation experiment, conducted by the Japanese Nuclear Energy Safety organization on high enriched mixed oxide fuel, is outlined. In a second part, the approach for fission gas release modelling, as implemented in the fuel performance code MACROS, is explained and a comparison between calculated and experimental results is made. The code MACROS is conceived to provide not only integral (rod average) results on fission product and fission gas retention and release, but also to calculate local concentrations (radial profiles). In this way, it is possible to compare results from post-irradiation examinations with calculated profiles.",

keywords = "FGR, EPMA, MOX, PIE, LWR, MACROS",

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AU - Lemehov, Sergei

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AU - Vos, Benedict

AU - Van den Berghe, Sven

AU - Verwerft, Marc

AU - Nakae, N.

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