Irradiation behavior of fast reactor fuel pins, 1; Evaluation of cesium behavior by coupling computer codes

Uwaba, Tomoyuki; Yokoyama, Keisuke; Ikusawa, Yoshihisa; Nemoto, Junichi*; Ishitani, Ikuo*; Ito, Masahiro*

no journal, , 

A computer code for the analysis of the overall irradiation performance of a fast reactor mixed-oxide (MOX) fuel element was coupled with a specialized code for the analysis of fission product cesium behaviors in a MOX fuel element. The coupled code system allowed for the analysis of the radial and axial Cs migrations, the generation of Cs chemical compounds and fuel swelling due to Cs-fuel-reactions in association with the thermal and mechanical behaviors of the fuel element. The coupled code analysis was applied to the irradiation performance of a fast reactor MOX fuel element attaining high burnup, showing consistency with post irradiation examinations.