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Article Dans Une Revue Journal of Nuclear Materials Année : 2022

Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

Résumé

This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad melting, oxidizing and/or reducing conditions within the furnace) performed with high burnup UO 2 fuel (i.e., up to 72 GWd/tU) and considering a coupling between irradiated fuel thermochemistry and a fission gas release model. The thermochemical calculations rely on the Thermodynamics of Advanced Fuels-International Database (TAF-ID) for the description of the phases likely to form from the 15 fission product considered in the fuel (Ba,

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Matériaux
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Dates et versions

hal-04018896 , version 1 (23-03-2023)

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A. Germain, J. Sercombe, C. Riglet-Martial, C. Introïni, L. Noirot, et al.. Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests. Journal of Nuclear Materials, 2022, 561, pp.153527. ⟨10.1016/j.jnucmat.2022.153527⟩. ⟨hal-04018896⟩
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