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

Inventory Estimation of ³⁶Cl and ⁴¹Ca in Concrete of Kori Unit 1

Mee Jang, Jong Myoung Lim, Hyun Chul Kim, Chang-Jong Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.1 pp.121-126

DOI:https://doi.org/10.7733/jnfcwt.2019.17.1.121 Download PDF Export Citation

The Dismantling and Disposal Strategy of a Biological Shield for Minimization of Radioactive Concrete Waste During Decommissioning of a Nuclear Power Plant

Cheol-Seung Cheon, Chang-Lak Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.355-367

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.355 Download PDF Export Citation

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

Aggregate Effects on γ-ray Shielding Characteristic and Compressive Strength of Concrete

Jeong-Hwan Oh, Young-Bum Mun, Jae-Hyung Lee, Hyun-Kook Choi, Sooseok Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.357-365

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.357 Download PDF Export Citation

An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility

Young-Yong Ji, Kyung-Kil Kwak, Dae-Seok Hong and Jong-Sik Shon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.2 pp.117-123

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Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition

Ju-Chan Lee, Ki-Seog Seo, Seong-Yeon Yoo

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.1 pp.37-43

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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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Structural Safety Analysis Of Rear Door in ACP Hotcell Facility for Spent Fuel Treatment

Kie-Chan Kwon, Jeong-Hoe Ku, Eun-Pyo Lee, Won-Myung Choung, Gil-Sung You, Won-Kyung Lee, Dong-Hak Kuk, Il-Je Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.1 pp.77-85

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Evaluation on the Radiological Shielding Design of a Hot Cell Facility

Il-Je Cho, Dong-Hak Kook, Jeong-Hoe Ku, Won-Myung Choung, Gil-Sung You, Eun-Pyo Lee, Seong-Won Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.1 pp.1-11

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