Criticality calculations for a BWR spent fuel pool

In this paper we present the methodology used for calculating the effective multiplication constant (Keff) for BWR spent fuel arrangements. The calculations were performed for the spent fuel pool specified in the Final Safety Analysis Report for the BWR Nuclear Plant at Laguna Verde, Veracruz. The computer codes RECORD and MIXQUIC were used to perform these calculations. The macroscopic cross sections for two energy groups were obtained with the RECORD code assuming 3 w/o U-235 enrichment and no gadolinium for the fuel elements and stainless steel surrounding the fuel assembly. The spent fuel racks geometry and cross sections were used along with the MIXQUIC code to perform the two-dimensional criticality calculations with no neutron leakage along the axial axis. Additional calculations were performed changing the temperature, fuel assemblies pitch and tube wall thickness. The results show that the multiplication constant obtained is less than the value of 0.95 required as a limit for the design of a spent fuel pool. (author). 3 refs, 5 figs, 1 tab