Fission product release from nuclear fuel I. Physical modelling in the ASTEC code

Author:

Brillant G.,Marchetto C.,Plumecocq W.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. High temperature oxidation of UO2 in steam–hydrogen mixtures;Abrefah;J. Nucl. Mater.,1994

2. Vaporization of UO2 at high temperatures and high pressures: a generic relation for volatilization;Alexander;High Temp. High Press.,1990

3. Barrachin, M., Chevalier, P., Cheynet, B., Fischer, E., 2006. A thermodynamic database for nuclear applications. In: MMSNF-5 Workshop. Nice, France.

4. Booth, A.H., 1957. A Method of Calculating Fission Gas Diffusion from UO2 Fuel and Its Application to the X-2 Loop Test. Tech. Rep. AECL-496, Atomic Energy of Canada Limited.

5. Interpretation and modelling of fission product Ba and Mo releases from fuel;Brillant;J. Nucl. Mater.,2010

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