![]() The first two – depletion, decay and gamma source calculation – were performed with ORIGEN-S, whereas for the last one – gamma transport and gamma dose rate calculations – MCNP6 was used. ![]() Calculations were divided into three phases. This activity, that follows up that carried out in the context of the Benchmark on dose rate calculations proposed by the Advanced Fuel Cycle Scenarios Expert Group of the OECD Nuclear Energy Agency, was developed in order to determine the real self-protection properties of fuel assemblies against the risk of diversion and theft of nuclear material for illegal use. This paper aims to investigate the main modeling aspects used to reproduce as accurately as possible the measurements of gamma dose rates of a spent fuel assembly performed on an irradiated UO 2 fuel assembly by thermoluminescence dosimeters during the course of nondestructive assay tests in 1981.
0 Comments
Leave a Reply. |
AuthorWrite something about yourself. No need to be fancy, just an overview. ArchivesCategories |