Radiation Shielding Effect due to Cracks in Concrete Silo Dry Storage Systems

Donghee Lee, Sunghwan Chung, Taehyung Na

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.3 pp.377-385

DOI:https://doi.org/10.7733/jnfcwt.2024.034 Download PDF Export Citation

Irradiation Effect on Silo Dry Storage Systems for CANDU Spent Nuclear Fuel

Taehyung Na, Yeji Kim, Donghee Lee, Taehyeon Kim, Sunghwan Chung

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.2 pp.117-128

DOI:https://doi.org/10.7733/jnfcwt.2024.013 Download PDF Export Citation

Dynamic Material Testing of Aged Concrete Cores From the Outer Wall of the High-Flux Advanced Neutron Application Reactor

JaeHoon Lim, Byoungsun Park, Jongmin Lim, Yun-Young Yang, Sung-Hyo Lee, Sang Soon Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.22 No.2 pp.139-144

DOI:https://doi.org/10.7733/jnfcwt.2024.018 Download PDF Export Citation

Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel

Taehyung Na, Youngoh Lee, Taehyeon Kim, Yongdeog Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.4 pp.503-516

DOI:https://doi.org/10.7733/jnfcwt.2023.032 Download PDF Export Citation

Review of Aging Management for Concrete Silo Dry Storage Systems

Donghee Lee, Sunghwan Chung, Yongdeog Kim, Taehyung Na

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.4 pp.531-541

DOI:https://doi.org/10.7733/jnfcwt.2023.038 Download PDF Export Citation

Design and Structural Safety Evaluation of Canister for Dry Storage System of PWR Spent Nuclear Fuels

Taehyung Na, Youngoh Lee, Taehyeon Kim, Donghee Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.4 pp.559-570

DOI:https://doi.org/10.7733/jnfcwt.2023.034 Download PDF Export Citation

Sensitivity Analysis of Thermal Parameters Affecting the Peak Cladding Temperature of Fuel Assembly

Ju-Chan Lee, Doyun Kim, Seung-Hwan Yu, Sungho Ko

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.21 No.3 pp.359-370

DOI:https://doi.org/10.7733/jnfcwt.2023.025 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

Analysis of Characteristics of Spent Fuels on Long-Term Dry Storage Condition

Suji Yoon, Kwangheon Park, Hyungju Yun

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.19 No.2 pp.205-214

DOI:https://doi.org/10.7733/jnfcwt.2021.19.2.205 Download PDF Export Citation

Safety Assessment of Aircraft Crash Accident Into Spent Nuclear Fuel Dry Storage Facility – A Review With Focus on Structural Evaluation

Sanghoon Lee

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.17 No.2 pp.263-278

DOI:https://doi.org/10.7733/jnfcwt.2019.17.2.263 Download PDF Export Citation

Review of Research on Chloride-Induced Stress Corrosion Cracking of Dry Storage Canisters in the United States

Hyoung-Gyu Park, Kwang-Heon Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.4 pp.455-472

DOI:https://doi.org/10.7733/jnfcwt.2018.16.4.455 Download PDF Export Citation

State-of-Arts of Primary Concrete Degradation Behaviors due to High Temperature and Radiation in Spent Fuel Dry Storage

Jin-Seop Kim, Donghak Kook, Jong-Won Choi, Geon-Young Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.16 No.2 pp.243-260

DOI:https://doi.org/10.7733/jnfcwt.2018.16.2.243 Download PDF Export Citation

Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions

Tae-Man Kim, Ho-Seog Dho, Chun-Hyung Cho, Jae-Hun Ko

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.391-402

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.391 Download PDF Export Citation

Preliminary Design of the Forced Gas Drying System for Spent Nuclear Fuel Dry Storage

Gyung-sun Chae, Kyung-wook Shin, Byeong-mok Park, Jae-hyun Han, Geon-hui Lee, Jae-seok Park

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.4 pp.403-409

DOI:https://doi.org/10.7733/jnfcwt.2017.15.4.403 Download PDF Export Citation

Review of Spent Nuclear Fuel Dry Storage Demonstration Programs in US

Sanghoon Lee, Daesik Yook

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.15 No.2 pp.135-149

DOI:https://doi.org/10.7733/jnfcwt.2017.15.2.135 Download PDF Export Citation

Activation Analysis of Dual-purpose Metal Cask After the End of Design Lifetime for Decommission

Tae-Man Kim, Ji-Young Ku, Ho-Seog Dho, Chun-Hyung Cho, Jae-Hun Ko

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.343-356

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.343 Download PDF Export Citation

Development of the Vacuum Drying Process for the PWR Spent Nuclear Fuel Dry Storage

Chang-Yeal Baeg, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.4 pp.435-443

DOI:https://doi.org/10.7733/jnfcwt.2016.14.4.435 Download PDF Export Citation

Status Analysis for the Confinement Monitoring Technology of PWR Spent Nuclear Fuel Dry Storage System

Chang-Yeal Baeg, Chun-Hyung Cho

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.14 No.1 pp.35-44

DOI:https://doi.org/10.7733/jnfcwt.2016.14.1.35 Download PDF Export Citation

Rock Cavern Storage of Spent Fuel

Won-Jin Cho, Sangki Kwon, Kyung-Soo Kim

Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.13 No.4 pp.301-313

DOI:https://doi.org/10.7733/jnfcwt.2015.13.4.301 Download PDF Export Citation