Experimental Evaluation of the Thermal Integrity of a Large Capacity Pressurized Heavy Water Reactor Transport Cask

Kyoung-Sik Bang, Yun-Young Yang, Woo-Seok Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.3 pp.357-364

DOI:https://doi.org/10.7733/jnfcwt.2022.028 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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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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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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