Abstract
Mixed oxide (MOX) developments with various compositions have been conducted as nuclear fuels. MOX with less than 15% Pu is used in light water reactors, and MOX with 20%–30% Pu content has been developed as driver fuels of fast reactors. Although similar phenomena occur during irradiation, different fuel performance codes have been developed for light water reactors and fast reactor fuels. This is due to the significant differences in fuel temperature during burning and the lack of Pu content dependence in the thermal and mechanical properties used in the analysis code. If the model showing the physical properties of fuel can be evaluated in the high-temperature range up to the melting point and effects, such as Pu content, MA content, O/M ratio, and burn up, it is possible to develop an integrated fuel performance code.
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