International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
Abstract
This paper presents the verification and validation of the source term calculation capability implemented in the reactor analysis code STREAM for the purpose of spent fuel analysis. Activity, decay heat, neutron and gamma source spectra of spent PWR fuel assemblies discharged are calculated. The verification is performed by comparison with ORIGEN-ARP calculations. Validation is done by comparing with experimental decay heat measurements from Swedish central storage facility for spent nuclear fuel, CLAB. The verification and validation results show good agreement with ORIGEN-ARP calculations and experimentally measured decay heat respectively.