Title of article
An efficient model for the analysis of fission gas release
Author/Authors
Bernard، نويسنده , , L.C. and Jacoud، نويسنده , , J.L. and Vesco، نويسنده , , P.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2002
Pages
10
From page
125
To page
134
Abstract
This paper presents the fission gas release (FGR) model that has been developed at Framatome ANP and incorporated into its fuel rod performance code COPERNIC in order to accurately predict FGR into pressurized water reactor fuel rods under normal and off-normal operating conditions including UO2, gadolinia and MOX fuels. The model is analytical, thus enabling fast and robust fuel rod calculations, a must within an industrial framework where safety evaluations may require the analyses of a full core and of a very large number of transients. Although the model is simple, it includes the most important FGR features: athermal, thermal, steady-state, and transient regimes, burst effect, rim formation, and MOX-type microstructure. The validation of the model covers 400 irradiated rods that include high burnups, high powers, short to long transients, and shows the quality of the prediction of the model in all types of conditions. As temperature is a key parameter that affects FGR, the COPERNIC thermal model is briefly described and its impact on fission gas released uncertainty is discussed.
Keywords
T0100 , U0200 , F0700 , F0500
Journal title
Journal of Nuclear Materials
Serial Year
2002
Journal title
Journal of Nuclear Materials
Record number
1355908
Link To Document