Monte Carlo Calculations Applied to Slowpoke Full-Reactor Analysis

Abstract

Stochastic Monte Carlo calculations are applied to the full-reactor analysis of the SLOWPOKE design. The temperature feedback of reactivity calculated by MCNP for either HEU or LEU core is in good agreement with the experimental data, with a k-eff bias of +3.3 mk for a HEU core and +6 mk for a LEU core. Two methods have been developed for core following: 1) MCNP (for transport calculation) in conjunction with WIMS (for fuel burnup advancement) and 2) SERPENT (that combines both transport and burnup capabilities), and both show very consistent results on core excess reactivity and detailed power distribution vs burnup and shim.