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Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions

Tae-Man Kim, Ho-Seog Dho, Chun-Hyung Cho, Jae-Hun Ko

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.391-402

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.391 Download PDF Export Citation
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A Study on Japanese Experience to Secure the Interim Storage Facility for Nuclear Spent Fuel

Kim, Kyung Min

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.351-357

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