Development of Model to Evaluate Thermal Fluid Flow Around a Submerged Transportation Cask of Spent Nuclear Fuel in the Deep Sea

Guhyeon Jeong, Sungyeon Kim, Sanghoon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.4 pp.411-428

DOI:https://doi.org/10.7733/jnfcwt.2022.043 Download PDF Export Citation

A Study on Thermal Load Management in a Deep Geological Repository for Efficient Disposal of High Level Radioactive Waste

Jongyoul Lee, Heuijoo Choi, Dongkeun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.4 pp.469-488

DOI:https://doi.org/10.7733/jnfcwt.2022.032 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

Repurposing a Spent Nuclear Fuel Cask for Disposal of Solid Intermediate Level Radioactive Waste From Decommissioning of a Nuclear Power Plant in Korea

Wonjune Mah, Chang-Lak Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.3 pp.365-369

DOI:https://doi.org/10.7733/jnfcwt.2022.024 Download PDF Export Citation

Chlorination of TRU/RE/SrO_x in Oxide Spent Nuclear Fuel Using Ammonium Chloride as a Chlorinating Agent

Dalsung Yoon, Seungwoo Paek, Sang-Kwon Lee, Ju Ho Lee, Chang Hwa Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.2 pp.193-207

DOI:https://doi.org/10.7733/jnfcwt.2022.016 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

iKSNF, the Control Tower for the R&D Program of SNF Storage and Disposal

Kyungsu Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.2 pp.255-258

DOI:https://doi.org/10.7733/jnfcwt.2022.020 Download PDF Export Citation

Code Requirements for Fuel Handling Equipment at Nuclear Power Plant

Sang-Gyoon Chang, Tae-Kyo Kang, Jong-Min Kim, Jong-Pil Jung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.20 No.1 pp.119-126

DOI:https://doi.org/10.7733/jnfcwt.2022.009 Download PDF Export Citation

Managing the Back-end of the Nuclear Fuel Cycle: Lessons for New and Emerging Nuclear Power Users From the United States, South Korea and Taiwan

Andrew Newman

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.4 pp.435-446

DOI:https://doi.org/10.7733/jnfcwt.2021.036 Download PDF Export Citation

Mechanical Integrity Evaluation on the Degraded Cladding Tube of Spent Nuclear Fuel Under Axial and Bending Loads During Transportation

Seong-Ki Lee, Dong-Hyo Lee, Joon-Kyoo Park, Jae-Hoon Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.4 pp.491-501

DOI:https://doi.org/10.7733/jnfcwt.2021.041 Download PDF Export Citation

A Systematic Approach for Mechanical Integrity Evaluation on the Degraded Cladding Tube of Spent Nuclear Fuel Under Transportation Pinch Force

Seong-Ki Lee, Joon-Kyoo Park, Jae-Hoon Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.3 pp.307-322

DOI:https://doi.org/10.7733/jnfcwt.2021.19.3.307 Download PDF Export Citation

Development of the Defect Analysis Technology for CANDU Spent Fuel

Yong-Chan Kim, Jong-Hyeon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.215-223

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.215 Download PDF Export Citation

Mechanochemical Approach for Oxide Reduction of Spent Nuclear Fuels for Pyroprocessing

Sung-Wook Kim, Seung Youb Han, Junhyuk Jang, Min Ku Jeon, Eun-Young Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.255-266

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.255 Download PDF Export Citation

Application of Logistic Simulation for Transport of SFs From Kori Site to an Assumed Interim Storage Facility

Young-Min Kim, Chang-Lak Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.1 pp.61-74

DOI:https://doi.org/10.7733/jnfcwt.2021.19.1.61 Download PDF Export Citation

Proposal of an Improved Concept Design for the Deep Geological Disposal System of Spent Nuclear Fuel in Korea

Jongyoul Lee, Inyoung Kim, HeeJae Ju, Heuijoo Choi, Dongkeun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.1-19

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.1 Download PDF Export Citation

Analyses on Thermal Stability and Structural Integrity of the Improved Disposal Systems for Spent Nuclear Fuels in Korea

Jongyoul Lee, Hyeona Kim, Inyoung Kim, Heuijoo Choi, Dongkeun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.21-36

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.21 Download PDF Export Citation

Scoping Calculations on Criticality and Shielding of the Improved KAERI Reference Disposal System for SNFs (KRS⁺)

In-Young Kim, Dong-Keun Cho, Jongyoul Lee, Heui-Joo Choi

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.37-50

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.37 Download PDF Export Citation

Assessment of Corrosion Lifetime of a Copper Disposal Canister Based on the Finnish Posiva Methodology

Heui-Joo Choi, Jongyoul Lee, Dongkeun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.51-62

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.51 Download PDF Export Citation

A Method for Operational Safety Assessment of a Deep Geological Repository for Spent Fuels

Jongtae Jeong, Dong-Keun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.63-74

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.63 Download PDF Export Citation

Safety Assessment on Long-term Radiological Impact of the Improved KAERI Reference Disposal System (the KRS⁺)

Heejae Ju, In-Young Kim, Youn-Myoung Lee, Jung-Woo Kim, Yongsoo Hwang, Heui-joo Choi, Dong-Keun Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.18 No.S pp.75-87

DOI:https://doi.org/10.7733/jnfcwt.2020.18.S.75 Download PDF Export Citation