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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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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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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Development of a Mass Transfer Model and Its Application to the Behavior of the Cs, Sr, Ba, and Oxygen ions in an Electrolytic Reduction Process for SF

Byung Heung Park, Dae-Seung Kang, Chung-Seok Seo, Seong-Won Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.2 pp.85-93

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