A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels

Sohee Cha, Kwangheon Park, Mun-Oh Kim, Jae-Hun Ko, Jin-Hyun Sung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.3 pp.303-313

DOI:https://doi.org/10.7733/jnfcwt.2023.022 Download PDF Export Citation

Fissile Measurement in Various Types Using Nuclear Resonances

YongDeok Lee, Seong-Kyu Ahn

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.2 pp.235-246

DOI:https://doi.org/10.7733/jnfcwt.2023.018 Download PDF Export Citation

CFD Analysis to Suppress Condensate Water Generated in Gas Sampling System of HANARO

SungHwan Cho, JongHyeon Lee, DaeYoung Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.2(E) pp.327-336

DOI:https://doi.org/10.7733/jnfcwt.2020.18.2(E).327 Download PDF Export Citation

Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications

Abdalla Abou-Jaoude, Anna Erickson, Nicolas Stauff

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.3 pp.359-367

DOI:https://doi.org/10.7733/jnfcwt.2018.16.3.359 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

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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