Quantitative Evaluation of Criticality According to the Major Influence of Applied with Burnup Credit on Dual-purpose Metal Cask

Ho-seog Dho, Tae-man Kim, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.2 pp.141-154

DOI:https://doi.org/10.7733/jnfcwt.2015.13.2.141 Download PDF Export Citation

Structural Safety Analysis of Lifting Device for Spent Fuel Dual-purpose Metal Cask

Tae-Chul Moon, Chang-Yeal Baeg, Si-Tae Yun, Byung-il Choi, In-su Jung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.12 No.4 pp.299-314

DOI:https://doi.org/10.7733/jnfcwt.2014.12.4.299 Download PDF Export Citation

Heat Transfer Analysis around Transport Cask under Transport Hood

Dong-Gyu Lee,Jae-Ho Park,In-Su Jung,Tae-Man Kim,Jeong-Hyun Yoon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.161-167

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Criticality Uncertainty Analysis of Spent Fuel Transport Cask applying Bmnup Credit

Gang ug Lee,Jea Ho Park,Do hyung Kim,Tae man Kim,Jeong hyun Yoon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.191-198

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The Corrosion Behavior of Cold-Rolled 304 Stainless Steel In Salt Spray Environments

M. F. Chiang, M.C. Young, J.Y. Huang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.93-98

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A Finite Element Modeling for the Puncture Drop Test of a Cask with the Failure of Impact Limiter

권기찬, 서기석, 유길성

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.7 No.1 pp.9-16

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Development of a Computer Program for the Analysis of Logistics of PWR Spent Fuels

Hewi-Joo Choi, Jeong-Hun Cha, Jongwon Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.2 pp.147-154

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The Test for Verifying a Tip-Over Analysis of a Dry Storage Cask

Don g-Hak Kim, Ki-Seog Seo, Ju-Chan Lee, Chun-Hyung Cho, Hyun-Kee Jang, Byung-Il Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.245-253

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A Structural Analytic Evaluation of a Connote Pad In a Spent Fuel Dry Storage Cask

Dong-Hak Kim, Ki-Seog Seo, Ju-Chan Lee, Yeon-Do Lee, Chun-Hyung Cho, Dae-Ki Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.2 pp.139-152

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On-Site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN-12 Transport Cask

Sung-Hwan Chung, Chang-yeal Baeg, Byung-Il Choi, Ke-Hyung Yang, Dae-Ki Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.51-58

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Thermal Analysis of a Spent Fuel Storage Cask under Normal and Off-Normal Conditions

Ju-Chan Lee, Kyung-Sik Bang, Ki-Seog Seo, Ho-Dong Kim, Byung-Il Choi, Heung-Young Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.13-22

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