MCNP Anaylsis of a D2O-Filled Fuel-Channel Penetration Through the End Shield

Abstract

Using a CANDU 9 reactor fuel channel as the model, a Monte Carlo analysis was performed which showed that, when the stainless-steel end-shield plug in the fuel channel was replaced with heavy-water coolant, the radiation dose rate from the fission product decay gammas was 2.4 mrem/hr at the end phase of the end-fittings 24 hours after reactor shutdown.