Comparison of Bundle Powers in an LVRF Core Using RFSP and MCNP

Abstract

This study determined whether replacing Natural Uranium fuel (NU) with Low Void Reactivity Fuel (LVRF) in two fuel channels at a Bruce B unit induces any additional uncertainties upon bundle powers calculated by the compliance code Simulation of Reactor Operation (SORO). The Monte Carlo N-Particle Transport Code (MCNP) was used as a surrogate for experimentation, while the Reactor Fuelling Simulation Program (RFSP) was used as a surrogate for SORO. The mean difference between bundle powers calculated by the two codes (~1%) was determined to be similar to the MCNP modelling uncertainty. Thus, no additional penalty was required for the use of SORO due to the presence of 2 LVRF channels within an NU core.