CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE

Abstract

The calculation of activation inventories is one of the key aspects in nuclear plants simulation. Burnup calculations provide information not only about fuel actinides transmutation but also about impact of fuel/constructor materials/coolant impurities on the material. The inventory evolution also determines radiological response of a material by nuclides production/decay rates quantification. Results of the isotopic kinetics code BPSD for activity and afterheat calculation validation by means of direct comparison afterheat obtained by code BPSD with experimental data obtained due to steel SS-304 and steel SS-316 samples irradiation by fusion neutron spectra at the FNS facility and with results of FISPACT-II calculation are presented in this paper. BPSD code is intended for carrying of transmutation calculations of materials in fast neutron fluxes. Nuclides transformation chains are based on ROSFOND and ABBN-RF data. BPSD and FISPACT-II calculations results conform to each other. Differences in results could be explained by differences between transformation chains and by using different evaluation neutron data bases.