Simulation Study on Atmospheric Emission Scenarios of Radioxenon Produced by the North Korea’s 6th Nuclear Test

Kihyun Park, Byung-Il Min, Sora Kim, Jiyoon Kim, Kyung-Suk Suh

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.2(E) pp.261-273

DOI:https://doi.org/10.7733/jnfcwt.2020.18.2(E).261 Download PDF Export Citation

A Suitability Study on the Indicator Isotopes for Graphite Isotope Ratio Method (GIRM)

Jinseok Han, Junkyung Jang, Hyun Chul Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.1 pp.83-90

DOI:https://doi.org/10.7733/jnfcwt.2020.18.1.83 Download PDF Export Citation

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

Production and Application of Domestic Input Data for Safety Assessment of Disposal

Chung-Kyun PARK¹⁾, Jae-Kwang LEE, Min-Hoon BAIK, Youn-Myoung LEE, Nak-Youl KO, Jong-Tae JEONG

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.10 No.3 pp.161-170

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Influence of Water Salinity on the Hydraulic Conductivity of Compacted Bentonite

Won-Jin Cho, Jin Seop Kim, Jong Won Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.4 pp.199-206

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An Investigation of Diffusion of Iodide Ion in Compacted Bentonite Containing Ag2O

Sung Paal Yim, Ji Hyun Lee, Heui-Joo Choi, Jong-Won Choi, Cheo Kyung Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.1 pp.33-40

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Multilateral Approaches to the Back-end of the Nuclear Fuel Cycle: Challenges and Possibilities

Ho Jin Ryu

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.269-277

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Assessment of Potential Impacts of the Proposals for Multilateralization of Nuclear Fuel Cycle

Joo Hyun Moon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.4 pp.339-346

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Computational Analysis for a Molten-salt 티ectrowinner with Liquid Cadmium Cathode

김광락, 정용주, 백승우, 김지용, 권상운, 윤달성, 김시형, 심준보, 김정국, 안도희, 이한수

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.1 pp.1-7

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Conceptual Reactive Transport Modeling of Long-term Concrete Degradation and Uranium Solubility

Byoung Young Choi, Yong Kwon Koh, Geon Young Kim, Si Won Yoo, Sang Won An, Dae Seok Bae

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.1 pp.35-44

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Investigation of Pyroprocessing Concept and Its Applicability as an Alternative Technology for Conventional Fuel Cycle

Jae-Hyung Yoo, Byung-Jik Lee, Han-Soo Lee, Eung-Ho Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.4 pp.283-295

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Multilateral Nuclear Cooperation in East Asia; The First Step Toward the Formation of a New Cooperation

Yong-Soo Hwang, Eun-Ha Kwon, Eun Jin Seo, Joo-ho Whang

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.3 pp.167-176

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