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Taehyung Na

Effect of applied current on the formation of defect in PWR nuclear fuel rods in resistance pressure welding process
2014 · Jong-Youl Park, Tae-Hyung Na, et al. · Journal of Nuclear Science and Technology · 23
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A study on characteristics of end plug resistance welding process in nuclear fuel rods by experiment and numerical simulation
2018 · Tae-Hyung Na, Suck-Joo Na, et al. · The International Journal of Advanced Manufacturing Technology · 18
Accelerated Formation of Oxide Layers on Zircaloy-4 Utilizing Air Oxidation and Comparison with Water-Corroded Oxide Layers
2023 · Shanmugam Mannan Muthu, Hyeon-Bae Lee, et al. · Materials · 12
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Quality monitoring of end plug resistance weldment for nuclear fuel rods by electrode displacement
2018 · Tae-Hyung Na, Bo-Hee Lee, et al. · The International Journal of Advanced Manufacturing Technology · 12
Algorithm development for quality monitoring on end plug resistance weldment of nuclear fuel rods
2015 · Tae-Hyung Na, Suck-Joo Na, et al. · The International Journal of Advanced Manufacturing Technology · 11
Realistic thermal analysis of the CANDU spent fuel dry storage canister
2023 · Tae Gang Lee, Taehyeon Kim, et al. · Nuclear Engineering and Technology · 6
Simulation-Based Characterization of Tube-Cap Resistance Butt Welding of Nuclear Fuel for Light Water Reactors and Development of Melted-Volume Prediction Models
2023 · Tae-Hyung Na · International Journal of Precision Engineering and Manufacturing · 5
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Conceptual Design, Development, and Preliminary Safety Evaluation of a PWR Dry Storage Module for Spent Nuclear Fuel
2022 · Taehyeon Kim, Kiyoung Kim, et al. · Applied Sciences · 5
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Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site
2024 · Tae Gang Lee, Taehyung Na, et al. · Nuclear Engineering and Technology · 4
Analysis of Foreign Substance Flow within the Weld Joint through Simulation in Pressurized Water Reactor Nuclear Fuel Rods
2023 · Taehyung Na, Taehyeon Kim, et al. · Applied Sciences · 4
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Structural Analysis of Thermal Diffusion and Non-Uniform Temperature Distribution along the Sidewall Thickness of STS316L during Gas Tungsten Arc Butt Welding
2024 · Taehyung Na, Gwang-Ho Jeong, et al. · Processes · 3
Verification of reliability of the burnup for PWR spent fuel of OPR1000 type
2025 · Donghee Lee, Yongdeog Kim, et al. · Nuclear Engineering and Technology · 1
Radiation Shielding Effect due to Cracks in Concrete Silo Dry Storage Systems
2024 · Donghee Lee, Sunghwan Chung, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Irradiation Effect on Silo Dry Storage Systems for CANDU Spent Nuclear Fuel
2024 · Taehyung Na, Yeji Kim, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Design and Structural Safety Evaluation of Transfer Cask for Dry Storage System of PWR Spent Nuclear Fuel
2023 · Taehyung Na, Youngoh Lee, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Design and Structural Safety Evaluation of Canister for Dry Storage System of PWR Spent Nuclear Fuels
2023 · Taehyung Na, Youngoh Lee, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Review of Aging Management for Concrete Silo Dry Storage Systems
2023 · Donghee Lee, Sunghwan Chung, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Preliminary Assessment of Thermal characteristics of CANDU spent fuel dry storage silo facility using CFD code
2023 · Tae-Gang Lee, Jae-Jun Jeong, et al. · Journal of Energy Engineering · 1
Development of a Two-Dimensional Bead Shape Prediction Algorithm for Fillet FCAW Considering Welding Speed and Torch Offset
2026 · Taehyung Na, Junsung Bae, et al. · Processes
Experimental characterization and performance evaluation of CANDU spent fuel prior to dry storage
2026 · Taehyung Na, Youngae Kim, et al. · Journal of Nuclear Materials
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Development of a simplified thermal analysis model for CANDU spent fuel dry storage basket
2026 · Tae Gang Lee, Taehyung Na, et al. · Nuclear Engineering and Technology
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Probabilistic failure assessment of spent nuclear fuel cladding based on critical crack depth
2026 · Sangil Choi, Ju-Chan Lee, et al. · Nuclear Engineering and Technology
Evaluation of Functional Capability for Spent Fuel Drops in PWR Spent Fuel Rack
2024 · Taehyung Na, Donghee Lee, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask
2024 · Taehyung Na, Youngoh Lee, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Simulation-based Characterization of Tube-cap Resistance Butt Welding of Nuclear Fuel for Light Water Reactors and Development of Melted-volume Prediction Models
2022 · Jong-Jung Lee, Young Whan Park, et al. · Research Square
Works count: 28
Citation count: 110
H-index: 6
I10-index: 5
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