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Volume 7: Operations, Applications and Components

DOI: 10.1115/pvp2017-66084

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Comparison Between Test and Analysis for Spent Nuclear Fuel Transportation Cask

Proceedings article published in 2017 by Woo-Seok Choi, Sangsoon Cho, Ki-Seog Seo, Kyoung-Sik Bang, Ju-Chan Lee, Seunghwan Yu
This paper was not found in any repository, but could be made available legally by the author.
This paper was not found in any repository, but could be made available legally by the author.

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Abstract

The storage and transport system are being developed in Korea. The spent fuels stored temporarily in wet storage at reactor site are scheduled to be transported to the interim storage in near term in Korea. To prepare the spent fuel transportation and storage, the dual purpose cask and concrete cask have been developed and submitted for the license approval. Safety evaluation test was conducted with 1/3 scaled model and so was analysis. Since numerical simulation results can be different based on the analysis models, the reliable FE model was generated through several revising process. The comparison between simulation and test was conducted by numerical simulation using this FE model. The reliable FE model made it possible to be proceeded stably by analysis and generated more realistic results compared to those of test. By the comparison between analysis and test results, the validity and appropriateness of the modeling technique and analysis methodology were verified.