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

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MACROS Benchmark Calculations And Analysis Of Fission Gas Release In MOX With High Content Of Plutonium. / Lemehov, Sergei; Jutier, Frédéric; Parthoens, Yves; Vos, Benedict; Van den Berghe, Sven; Verwerft, Marc; Nakae, N.

In: Progress in Nuclear Energy, Vol. 57, 06.03.2012, p. 117-124.

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@article{b71d3e2a19ed4e7aacb422b20d80ccfc,
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",
author = "Sergei Lemehov and Fr{\'e}d{\'e}ric Jutier and Yves Parthoens and Benedict Vos and {Van den Berghe}, Sven and Marc Verwerft and N. Nakae",
note = "Score = 10",
year = "2012",
month = mar,
day = "6",
doi = "10.1016/j.pnucene.2011.12.010",
language = "English",
volume = "57",
pages = "117--124",
journal = "Progress in Nuclear Energy",
issn = "0149-1970",
publisher = "Elsevier",

}

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TY - JOUR

T1 - MACROS Benchmark Calculations And Analysis Of Fission Gas Release In MOX With High Content Of Plutonium

AU - Lemehov, Sergei

AU - Jutier, Frédéric

AU - Parthoens, Yves

AU - Vos, Benedict

AU - Van den Berghe, Sven

AU - Verwerft, Marc

AU - Nakae, N.

N1 - Score = 10

PY - 2012/3/6

Y1 - 2012/3/6

N2 - 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.

AB - 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.

KW - FGR

KW - EPMA

KW - MOX

KW - PIE

KW - LWR

KW - MACROS

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_119865

UR - http://knowledgecentre.sckcen.be/so2/bibref/8928

U2 - 10.1016/j.pnucene.2011.12.010

DO - 10.1016/j.pnucene.2011.12.010

M3 - Article

VL - 57

SP - 117

EP - 124

JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

SN - 0149-1970

ER -

ID: 108821