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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
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A Study on the Wigner Energy Release Characteristics of Irradiated Graphite of KRR-2

Gyeong Hwan Jeong, Sei-Hun Yun, Dong-Gyu Lee, Chong-Hun Jung, Keun Woo Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.209-216

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Dose Evaluation of Neutron within Containment Building of a CE type Nuclear Power Plant

Tae-Wook Kim, Jae-Mun Han, Kyung-Doek Kim, Cheol-Whan Yun, Jang-Soo Suh, Young-Jae Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.3 No.1 pp.23-30

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Efficiency Calibration of HPGe Detector in Normal ana Coincidence Mode for the Determination of Prompt Gamma-ray

Byoung-Chul Song, Yong-Joon Park, Kwang-Yong Jee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.2 No.2 pp.97-104

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