Radiation Safety Assessment of CANDU Spent Fuel Disposal System
Kook, Dong-Hak;Cho, Dong-Keun;Choi, Heui-Joo;
ABSTRACT
The purpose of this article is to evaluate the radiation safety of CANDU spent fuel disposal system by using MCNPX which was revised in order to improve disposal efficiency. This research analyzed every system components's configuration, dimension and material. Geometric modeling and dose assessment for each system components showed that dose results for inner components had high values, but final disposal system had enough margin for radiation safety.
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