A procedure for verification of Studsvik's spent nuclear fuel code SNF

摘要

Studsvik's approach to spent nuclear fuel analyses combines isotopic concentrations and cross-sections, calculated by the lattice physics codes, with core irradiation history data from reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code Spent Nuclear Fuel (SNF) to predict spent nuclear fuel characteristics. The procedure for verification and validation of SNF is outlined in this paper which includes verification of the decay data as well as the numerical methods where they are applied into. The paper presents the applicability of SNF to analyses of spent nuclear fuel in comparisons to well established and recognized code in the spent fuel analyses field, ORIGEN, SCALE v6.2.2.