A Comparative Study on Gamma-ray Measurement and MCNP Simulation for Precise Measurement of Spent Nuclear Fuel Burnup

Sohee Cha, Kwangheon Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.2 pp.129-137

DOI:https://doi.org/10.7733/jnfcwt.2024.016 Download PDF Export Citation

Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask

Taehyung Na, Youngoh Lee, Yeji Kim, Donghee Lee, Taehyeon Kim, Kiyoung Kim, Yongdeog Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.2 pp.201-210

DOI:https://doi.org/10.7733/jnfcwt.2024.014 Download PDF Export Citation

Isotopic Analysis of Decay Heat Contributors From Actinides and Fission Fragments of Spent Nuclear Fuel for Intermediate- and Long-Term Storage Times

Amir Mohammad Al-Ramady

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.1 pp.1-7

DOI:https://doi.org/10.7733/jnfcwt.2024.004 Download PDF Export Citation

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

Nuclear Criticality Analyses of Two Different Disposal Canisters for Deep Geological Repository Considering Burnup Credit

Hyungju Yun, Manho Han, Seo-Yeon Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.4 pp.501-510

DOI:https://doi.org/10.7733/jnfcwt.2022.038 Download PDF Export Citation

Review of Instant Release Fractions of Long-lived Radionuclides in CANDU and PWR Spent Nuclear Fuels Under the Geological Disposal Conditions

Heui Joo Choi, Yang-Hyun Koo, Dong-Keun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.2 pp.231-241

DOI:https://doi.org/10.7733/jnfcwt.2022.018 Download PDF Export Citation

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

Investigation of PWR Spent Fuels for the Design of a Deep Geological Repository

Dong-Keun Cho, Jungwoo Kim, In-Young Kim, Jong-Youl Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.3 pp.339-346

DOI:https://doi.org/10.7733/jnfcwt.2019.17.3.339 Download PDF Export Citation

The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask

Ho-Seog Dho, Tae-Man Kim, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.411-422

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.411 Download PDF Export Citation

Quantitative Evaluation of Criticality According to the Major Influence of Applied with Burnup Credit on Dual-purpose Metal Cask

Ho-seog Dho, Tae-man Kim, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.2 pp.141-154

DOI:https://doi.org/10.7733/jnfcwt.2015.13.2.141 Download PDF Export Citation

Criticality Uncertainty Analysis of Spent Fuel Transport Cask applying Bmnup Credit

Gang ug Lee,Jea Ho Park,Do hyung Kim,Tae man Kim,Jeong hyun Yoon

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.9 No.3 pp.191-198

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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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Development of a Simplified Source Term Estimation Model for a Spent Fuel from Westinghouse-type Reactors

조동건, 국동학, 최희주, 최종원

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.8 No.3 pp.239-245

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Reference Spent Nuclear Fuel for Pyroprocessing Facility Design

조동건, 윤석균, 최희주, 최종원, 고원일

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.6 No.3 pp.225-232

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