A Study on Radiation Safety Evaluation for Spent Fuel Transportation Cask

Young-Hwan Choi, Jae-Hun Ko, Dong-Gyu Lee, In-Su Jung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.4 pp.375-387

DOI:https://doi.org/10.7733/jnfcwt.2019.17.4.375 Download PDF Export Citation

Investigation of PWR Spent Fuels for the Design of a Deep Geological Repository

Dong-Keun Cho, Jungwoo Kim, In-Young Kim, Jong-Youl Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.3 pp.339-346

DOI:https://doi.org/10.7733/jnfcwt.2019.17.3.339 Download PDF Export Citation

The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask

Ho-Seog Dho, Tae-Man Kim, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.411-422

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.411 Download PDF Export Citation

An Analysis on the Deep Geological Disposal Concepts Considering the Spent Fuel Length

Jongyoul LEE, Hyeona KIM, Minsoo LEE, Heuijoo CHOI, Keonyoung KIM

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.3 pp.201-209

DOI:https://doi.org/10.7733/jnfcwt.2015.13.3.201 Download PDF Export Citation

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

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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Development of a Simplified Source Term Estimation Model for a Spent Fuel from Westinghouse-type Reactors

조동건, 국동학, 최희주, 최종원

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.239-245

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Reference Spent Nuclear Fuel for Pyroprocessing Facility Design

조동건, 윤석균, 최희주, 최종원, 고원일

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.225-232

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Study of morphology on the Oxidation and the Annealing of High Burn-hp UO2 Spent Fuel

Dae Ho Kim, Jae Geun Bang, Yong Sik Yang, Keun Woo Song, Hyung Kwon Lee, Hyung Moon Kwon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.4 pp.301-307

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