Experimental Validation of Models for Radiation Dose Rate from CANDU Spent Fuel

Abstract

The standard calculational techniques and shielding codes ORIGEN, ANISN and QAD-CG have been used to calculate dose rates from the irradiated fuel bundles for the Douglas Point dry irradiated fuel storage facility. The measured dose rates from fuel trays under water were translated into an estimate of fuel decay times to identify 'cool' (eight years or longer) bundles in the bay, The radiation dose rates from the welding station, transport flask and concrete canisters containing the fuel basket(s) were measured and compared with those of calculations.