Title: The data requirements for the verification and validation of a fuel performance code - the TRANSURANUS perspective
Authors: DI MARCELLO VALENTINORONDINELLA VincenzoVAN DE LAAR JacquesVAN UFFELEN Paul
Other Contributors: SCHUBERT Arndt
Citation: WWER Fuel Performance, Modelling and Experimental Support p. 321-334
Publisher: Bulgarian Academy of Sciences, Institute for Nuclear Research and Nuclear Energy
Publication Year: 2013
JRC N°: JRC80862
ISSN: 1313-4531
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC80862
Type: Articles in periodicals and books
Abstract: In general, the verification and validation of a fuel performance code like TRANSURANUS consists of three basic steps: a) verifying the correctness and numerical stability of the sub-models; b) comparing the sub-models with experimental data; c) comparing the results of the integrated fuel performance code with experimental data Only the second and third step of the V&V relies on experimental information. This scheme can be further detailed according to the physical origin of the data: on one hand in-reactor experimental data are generated in the course of the irradiation; on the other hand ex-reactor ('out-of-pile') data are obtained from various post-irradiation examinations (PIE). For both categories, we will first discuss the V&V of sub-models of TRANSURANUS that is related to separate aspects of the fuel behaviour: this includes the radial variation of the composition and fissile isotopes, the thermal properties of the fuel (e.g. thermal conductivity, melting temperature etc.), the mechanical properties of fuel and cladding (e.g. elastic constants, creep properties), as well as the models for the fission product behaviour. Secondly, the integrated code verification will be addressed as it treats various aspects of the fuel behaviour, including the geometrical changes in the fuel and the gas pressure and composition of the free volume in the rod.
JRC Directorate:Nuclear Safety and Security

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