Hydride embrittlement resistance of Zircaloy-4 and Zr-Nb alloy cladding tubes and its implications on spent fuel management S Kim, JH Kang, Y Lee Journal of Nuclear Materials 559, 153393, 2022 | 29 | 2022 |
Suppressed hydride precipitation in the welding zone of a zirconium-based alloy cladding tube S Kim, JH Kang, Y Lee Journal of Nuclear Materials 580, 154406, 2023 | 9 | 2023 |
Recrystallization and grain growth of Zr-Nb-Sn alloy in 400–500° C and effect on hydride embrittlement S Kim, D Son, JH Kang, Y Lee Journal of Nuclear Materials 583, 154477, 2023 | 8 | 2023 |
Comparison of Hydride Embrittlement of Zircaloy-4 and Zr-Nb Alloy Cladding Tubes S Kim, JH Kang, Y Lee Abstracts of Proceedings of the Korean Radioactive Waste Society SPRING 2021 …, 2021 | 5 | 2021 |
Investigation of Hydrogen Induced Cladding Embrittlement in Spent Fuel Pool Environment S Kim, Y Lee Proceedings of the Korean Radioactive Waste Society SPRING 2020 18 (1), 71-72, 2020 | 4 | 2020 |
Hydride Embrittlement Analysis on the End Cap Welded Zone and Heat Affected Zone of Zr-Nb alloy tube S Kim, Y Lee Trans. Ofthe Korean Nucl. Soc. Virtual Autumn Meet 1, 1-4, 2021 | 3 | 2021 |
Mechanism of Abrupt Ductile-To-Brittle Transition of Hydrided Zircaloy and Improving Resistance to Hydride Embrittlement Via Grain Size Control S KIM, Y LEE, J KANG TopFuel, 2021 | 3 | 2021 |
Feasibility analysis of UAV technology to improve tactical surveillance in South Korea's rear area operations S Kim Monterey, California: Naval Postgraduate School, 2017 | 2 | 2017 |
Effect of reduced hydride connectivity on the mechanical strength of Zr-Nb-Sn alloy via grain growth S Kim, Y Lee Korean Nuclear Society 2023 (Spring), 2023 | | 2023 |
The status of the U.S HALEU/LEU+ supply program and its implications on the Korean advanced reactor research and development S Kim, Y Lee Korean Nuclear Society 2023 (Spring), 2023 | | 2023 |
Suppressed Hydride Precipitation in the Welding Zone of Zircaloy Cladding Tube S Kim, JH Kang, Y Lee Available at SSRN 4200033, 0 | | |