Drop Impact Analysis for Basket Design Selection in Spent Fuel Shipping Cask for Korean Standard Nuclear Power Plant

摘要

This paper describes a structural evaluation process for optimal basket structure design of the spent nuclear fuel shipping cask for Korean standard nuclear power plant. The cask is assumed to store 18 PWR fuel assemblies with water for transport. Code and standard requires the cask should remain safe with no release of radioactive material to public in both normal transport and hypothetical accident condition. Depending upon how the basket structure is supported in the cask, there could be a couple of options like an insertion round plate type and a weld plate type, and the final basket design should be picked up thru engineering evaluation. Therefore, preliminary impact analyses for a typical case of the 9m drop accident for the two options are executed with review of fabrication efficiency. As a result, the cell insertion type design turns out to be the better in viewpoint of structural integrity and fabrication.