Optimal Neutron Absorber Location to Mitigate End Flux Peaking in CANDU Fuel Bundles

Abstract

End flux peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles. These peaks lead to an increase in fission rate and therefore greater heat generation. It is known that addition of neutron absorbers into fuel bundles can help mitigate EFP, yet implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. Monte Carlo N-Particle code (MCNP) 6.1 was used to simulate the addition of neutron absorbers strategically within various locations within the fuel bundle. This paper will present results on the optimal absorber location.