Simplified Approach to Source Term Estimation for SMRs

Abstract

Source Term refers to the quantity and type of radioactive materials available for release to the environment following a nuclear accident. Detailed simulations, using a code such as MAAP4-CANDU, are typically employed to estimate the Source Term. This paper presents a simplified approach for estimating the Source Term, utilizing parameters such as: fission product yields, fuel composition, radionuclide release fractions, and reactor thermal power. The obtained results are verified against published data for the Source Term of a CANDU reactor, following a postulated severe accident. This method will be applied to Small Modular Reactors, for a quick estimation of the Source Term.