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Hyungju Yun

Observed names: Hyung-Ju Yun, Hyungjoo Yoon
ORCID: 0000-0003-4716-4822
Observed ORCID: 0000-0003-4716-4822
OpenAlex ID: A5005407376
A Criticality Analysis of the GBC-32 Dry Storage Cask with Hanbit Nuclear Power Plant Unit 3 Fuel Assemblies from the Viewpoint of Burnup Credit
2016 · Hyungju Yun, Do-Yeon Kim, et al. · Nuclear Engineering and Technology · 13
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Radiological Safety Assessment for Deep Geological Disposal of High‐Level Radioactive Waste
2024 · Jiseon Jang, Mi-Seon Jeong, et al. · International Journal of Energy Research · 12
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An efficient evaluation of depletion uncertainty for a GBC-32 dry storage cask with PLUS7 fuel assemblies using the Monte Carlo uncertainty sampling method
2017 · Hyungju Yun, Kwangheon Park, et al. · Annals of Nuclear Energy · 11
Predicting radionuclide behavior in deep geological repositories using graph convolutional long short-term memory
2025 · Dae Seong Jeong, Jinuk Lee, et al. · Journal of Hazardous Materials · 6
Thermal analyses of TN-24P dry storage cask with heterogeneous fuel assembly modeling
2021 · Hyungju Yun, Jaebin Shin, et al. · Progress in Nuclear Energy · 5
Physics-guided deep learning surrogate model with graph attention for long-term radionuclide transport prediction in deep geological repositories
2025 · Dae Seong Jeong, Jinuk Lee, et al. · Journal of Hazardous Materials · 4
Nuclear Criticality Analyses of Two Different Disposal Canisters for Deep Geological Repository Considering Burnup Credit
2022 · Hyungju Yun, Manho Han, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 2
Thermal Analyses of Deep Geological Disposal Cell With Heterogeneous Modeling of PLUS7 Spent Nuclear Fuel
2023 · Hyungju Yun, Min-Seok Kim, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Analysis of Characteristics of Spent Fuels on Long-Term Dry Storage Condition
2021 · Suji Yoon, Kwangheon Park, et al. · Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT) · 1
Numerical Assessment of Repository Stability Based on Preliminary Disposal Concept for High-Level Radioactive Waste in Korea
2026 · Dae-Sung Cheon, Min-Jun Kim, et al. · ISRM European Rock Mechanics Symposium (EUROCK)
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Conceptual Design and Performance Assessment of the KORADIS System in South Korea
2026 · Hyung-Ju Yun, Chang-Min Shin, et al. · International Journal of Energy Research
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Works count: 11
Citation count: 55
H-index: 5
I10-index: 3
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