Affiliation:
1. Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
2. Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Abstract
In order to develop a minor actinide (MA) containing MOX (MA-MOX) fuel design method, the analysis models to predict irradiation behavior of MA-MOX fuel have to be developed and the accuracy of the irradiation behavior analysis code should be evaluated with the results of post-irradiation examinations (PIEs) for MA-MOX fuels. In this study, we developed the computer module TRANSIT (Thermal Property and Vapor Pressure Analysis Module for Minor Actinide Containing MOX Fuel) to compute thermal properties of MA-MOX fuel. TRANSIT can give thermal conductivity, melting temperature and vapor pressures of MA-MOX. By using this module, we improved the thermal behavior analysis code DIRAD and developed the DIRAD-TRANSIT code system to compute the irradiation behavior of MA-MOX fuel. This system was verified with the results of PIEs for the conventional MOX fuels and the MA-MOX fuels irradiated in the experimental fast reactor JOYO. As the result of the verification, we determined that the DIRAD-TRANSIT code system would precisely predict the fuel thermal behavior, i.e. fuel temperature and fuel restructuring, for oxide fuels containing several percent minor actinides.
Publisher
American Society of Mechanical Engineers
Cited by
2 articles.
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