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Article Dans Une Revue Journal of Nuclear Materials Année : 2019

Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident

Résumé

The chemical behaviour of the main elements present in a PWR irradiated fuel sample (UO$_2$ fuel, Zr from the Zircaloy-cladding, Pu, Np, and fission products such as Ba, Ce, Cs, Gd, I, La, Mo, Nd, Pd, Rh, Ru, Sr, Tc, Te, etc.) submitted to a nuclear severe accident type sequence (VERDON-1 experiment) has been investigated by thermodynamic calculations using the TAF-ID database. Particular emphasis has been placed on the chemical behaviour of the fission products Ba, Cs, Mo, and Zr, and the interactions between the Zircaloy-cladding and the UO$_2$ matrix. Calculation results have been compared to experimental observations completed during the VERDON-1 experiment (instantaneous release of fission products and final chemical state of elements in the sample). Results presented in this manuscript do not account for non-equilibrium phenomena that have a major impact on fission product behaviour (e.g., chemical diffusion, mass transport induced by temperature gradients in the fuel pellet, etc.). None the less, these TAF-ID calculations have described accurately the melting of the sample following the formation of a mixed (U,Zr)O$_2$-x phase because of the interaction between the fuel and the Zircaloy-cladding. Furthermore, calculations have assisted in the explanation of the instantaneous released fractions observed for Ba and Mo during the experiment (as a function of the experiment atmosphere and temperature).
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Dates et versions

hal-03487013 , version 1 (20-12-2021)

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Paternité - Pas d'utilisation commerciale

Identifiants

Citer

E. Geiger, C. Guéneau, Y. Pontillon, E.C. Corcoran. Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident. Journal of Nuclear Materials, 2019, 522, pp.294 - 310. ⟨10.1016/j.jnucmat.2019.05.027⟩. ⟨hal-03487013⟩
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