A Study on Diffusion Approximations to Neutron Transport Boundary Conditions

Taewan Noh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.203-209

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.203 Download PDF Export Citation

Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation

Taewan Noh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.211-221

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.211 Download PDF Export Citation

Development Status for Commercialization of Spent Nuclear Fuel Transportation and Dry Storage System Technology

Chang-Yeal Baeg, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.271-279

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.271 Download PDF Export Citation

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 Study on the Radiation Source Effect to the Radiation Shielding Analysis for a Spent-Fuel Cask Design with Burnup-Credit

Kyung-O KIM, Sooo Youog KIM, Jaehoon Ko, Gangug Lee, Taeman Kim, Jeonghyun Yoon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.2 pp.73-80

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Safett evaluation of type B transport container for tritium storage vessel

이민수, 백승우, 김광락, 안도희, 임성괄, 정홍석, 최희주, 최종원, 손순환, 송규민

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.2 pp.155-169

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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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