The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Online ISSN : 2424-2934
2023.30
Session ID : 1301
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MULTIPHYSICS FISSION GAS RELEASE AND SWELLING BEHAVIOR FOR URANIUM-PLUTONIUM MIXED OXIDE FUELS IN A LEAD-COOLED FAST REACTOR
Jingyu GuoWenzhong Zhou
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Abstract

Fission gas release and swelling were modeled by Comsol Multiphysics in Mixed Oxide Fuel (MOX). This model is mainly based on the Operational Gas RElease and Swelling (OGRES) model. In previous studies, the fission gas release and swelling are primarily related to burnup, time, and temperature. In this model it is assumed a spherical grain at the fuel pellet inner radius. The grain is 2D axisymmetric geometry in Comsol Multiphysics. Fission gas atom generation, gas atom diffusion, gas atom diffusion into the bubble, bubble resolution, gas bubble nucleation, gas bubble migration to the grain boundary, bubble pressure, gas bubble swelling, grain growth, oxygen to metal atomic ratio, fuel porosity, fuel thermal conductivity, heat generation rate, pore velocity, pore concentration, plutonium migration, and fuel material properties are considered into this model. All relevant formulations are input into the model. The results include grain size, gas bubble diameter, gas bubble concentration and the number of gas atoms per bubble, gas atom diffusion coefficient, bubble diffusion coefficient and surface diffusion coefficient with temperature, fission gas release with time, as well as swelling with time and radius. These results will finally be analyzed and compared with other modeling outcomes and experiments.

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© 2023 The Japan Society of Mechanical Engineers
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