SEARCH
Search Details
Jang Sunghyon
| Faculty of Engineering Applied Quantum Science and Engineering Quantum Energy Engineering | Assistant Professor |
Researcher basic information
■ Degree■ URL
researchmap URLホームページURL■ Various IDs
Researcher number
- 90782300
- Bachelor's degree program, School of Engineering
- Master's degree program, Graduate School of Engineering
- Doctoral (PhD) degree program, Graduate School of Engineering
Research activity information
■ Awards- Mar. 2023, 日本原子力学会リスク部会, 第5回日本原子力学会リスク部会奨励賞
マルチユニット影響による環境変化を考慮した人的過誤確率に関する研究 – ファジィ推論による熟練度及び手順書の影響評価
張 承賢 - Mar. 2023, 日本原子力学会 北海道支部, 支部奨励賞
マルチユニット影響による環境変化を考慮した人的過誤率評価（１）ファジィ推論による熟練度及び手順書の影響評価
張承賢 - Mar. 2022, 原子力学会リスク部会, 第3回日本原子力学会リスク部会奨励賞
ファジ推論を用いてマルチユニット影響を考慮した人的過誤率評価
張 承賢 - Mar. 2021, 日本原子力学会リスク部会, 第1回日本原子力学会リスク部会奨励賞
余震の影響を考慮した地震と溢水の複合事象の確率論的リスク評価手法
張 承賢 - Mar. 2013, IAEA, IAEA YOUNG SCIENTIST VIDEO AWARD
Numerical Investigation of Experimental Methodology for Simulating Self-Wastage Phenomenon using Simulant Material
Sunghyon Jang
- Dynamic probabilistic risk assessment of seismically induced internal flooding considering aftershock effects using physics-based flood propagation and fragility models
Sunghyon Jang; Jaehyun Cho
Journal of Nuclear Science and Technology, 11 Aug. 2026
English, Scientific journal - Development of methods to model the uncertainty distribution of seismically induced joint failure probability for seismic probabilistic risk assessment
Shota Soga; Eishiro Higo; Sunghyon Jang; Munemichi Kawaguchi; Hiromichi Miura
Journal of Nuclear Science and Technology, 10 Jul. 2026
Scientific journal - Subcooled forced convection boiling on a vertical surface and gas-liquid structure near the heat transfer surface
Sunghyon Jang
Journal of Nuclear Science and Technology, Mar. 2026, [Peer-reviewed], [Lead author] - An analytical comparison of the multivariate normal model and the Reed–McCann procedure
Soga, S.; Higo, E.; Jang, S.; Kawaguchi, M.; Miura, H.
Reliability Engineering and System Safety, 265, 2026
Scientific journal - A study on quantification for the impact of stress and time margin on human error probability assessment in nuclear power plant using fuzzy inference
Jang, S.; Sawa, K.
Nuclear Engineering and Technology, 57, 5, 2025
Scientific journal - Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations
Kubo, K.; Jang, S.; Takata, T.; Yamaguchi, A.
Journal of Nuclear Science and Technology, 60, 4, 2023
Scientific journal - Simulation-based dynamic probabilistic risk assessment of an internal flooding-initiated accident in nuclear power plant using THALES2 and RAPID
Kubo, K.; Zheng, X.; Tanaka, Y.; Tamaki, H.; Sugiyama, T.; Jang, S.; Takata, T.; Yamaguchi, A.
Proceedings of the Institution of Mechanical Engineers Part O Journal of Risk and Reliability, 237, 5, 2023
Scientific journal - Analysis of steam generator tube rupture accidents for the development of mitigation strategies
Bang, J.; Choi, G.H.; Jerng, D.-W.; Bae, S.-W.; Jang, S.; Ha, S.J.
Nuclear Engineering and Technology, 54, 1, 2022
Scientific journal - Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants
Kubo, K.; Jang, S.; Takashi, T.; Yamaguchi, A.
Journal of Nuclear Science and Technology, 59, 3, 2022
Scientific journal - Qualitative Risk Analysis of Primary Containment Vessel Venting using STAMP/STPA,格納容器ベントにおける STAMP/STPA を用いた定性的システムリスク分析
Hirokawa, N.; Yamaguchi, A.; Takata, T.; Jang, S.
Transactions of the Atomic Energy Society of Japan, 21, 4, 2022
Scientific journal - Application of continuous Markov-chain Monte-Carlo method to multi-unit risk evaluations considering interdependence of accident progression among multiple units
Sawada, K.; Yamamoto, A.; Endo, T.; Sato, C.; Maeda, K.; Jang, S.
Journal of Nuclear Science and Technology, 58, 12, 2021
Scientific journal - Development of source term evaluation method applicable to dynamic PRA,ダイナミック PRA に適用可能なソースターム評価手法の開発
Nakamura, K.; Jang, S.; Yamaguchi, A.
Transactions of the Atomic Energy Society of Japan, 19, 1, 2020
Scientific journal - A novel method for risk-informed decision-making under non-ideal Instrumentation and Control conditions through the application of Bayes’ Theorem
Tan, T.G.; Jang, S.; Yamaguchi, A.
Reliability Engineering and System Safety, 188, 2019
Scientific journal - Experimental and statistical study on fracture boundary of non-irradiated Zircaloy-4 cladding tube under LOCA conditions
Narukawa, T.; Yamaguchi, A.; Jang, S.; Amaya, M.
Journal of Nuclear Materials, 499, 2018
Scientific journal - Dynamic scenario quantification for level 2 PRA of sodium-cooled fast reactor based on continuous Markov chain and Monte Carlo method coupled with meta-model of thermal–hydraulic analysis
Jang, S.; Yamaguchi, A.
Journal of Nuclear Science and Technology, 55, 8, 2018
Scientific journal - Uncertainty quantification of fracture boundary of pre-hydrided Zircaloy-4 cladding tube under LOCA conditions
Narukawa, T.; Yamaguchi, A.; Jang, S.; Amaya, M.
Nuclear Engineering and Design, 331, 2018
Scientific journal - Risk Assessment Strategy for Decommissioning of Fukushima Daiichi Nuclear Power Station
Yamaguchi, A.; Jang, S.; Hida, K.; Yamanaka, Y.; Narumiya, Y.
Nuclear Engineering and Technology, 49, 2, 2017
Scientific journal - A Numerical Design and Feasibility Study of Self-Wastage Experiment Using Simulant Material in a Sodium Fast Reactor
Jang, S.; Takata, T.; Yamaguchi, A.
Nuclear Engineering and Technology, 48, 2, 2016
Scientific journal - Numerical approach for quantification of selfwastage phenomena in sodium-cooled fast reactor
Jang, S.; Takata, T.; Yamaguchi, A.; Uchibori, A.; Kurihara, A.; Ohshima, H.
Nuclear Engineering and Technology, 47, 6, 2015
Scientific journal
- エネルギー環境システム工学特別ラボラトリーセミナー, 2024年, 修士課程, 工学院
- エネルギー環境システム工学特別ラボラトリーセミナー, 2024年, 博士後期課程, 工学院
- 応用数学演習Ⅱ, 2024年, 学士課程, 工学部
■ Research Themes
- 小型モジュール炉を対象とした過酷状況下タスク分析モデル・人間信頼性評価モデルの開発
原子力システム研究開発事業
Oct. 2025 - Mar. 2028
張承賢
文部科学省, 若手, 北海道大学, Principal investigator - Development of event progression inference model under a severe accident condition in a nuclear power plant using a machine learning and surrogate model
Grants-in-Aid for Scientific Research
01 Apr. 2021 - 31 Mar. 2023
張 承賢
本年度の主な研究成果として、原子力重大事故時のシステムの挙動を評価するシビアアクシデント解析コードを用いて事象進展について解析を行い、得られたデータを用いて代替統計モデルを用いた機械学習モデルを構築することであったが、研究機関の移動に伴いシビアアクシデントコードの入手が予定通りできなかったため、主に他の例題を使った代替統計モデルの構築、機械学習の試行を主に実施した。また機械学習用のソフトの導入について検討を行った。
米国原子力規制委員会が開発したMELCORコードの入手が研究機関の移動に伴い、新しい手続き等が必要なため、今後研究において使用可能であるか不透明であるため、MELCORコードを代替するシビアアクシデント解析コードを検討している状況である。
Japan Society for the Promotion of Science, Grant-in-Aid for Early-Career Scientists, Hokkaido University, 21K14561 - Development of Dyanamic Risk Analysis Methodology Considering Interunit Dependency at Multiunit Site.
Grants-in-Aid for Scientific Research
01 Apr. 2018 - 31 Mar. 2022
JANG SUNGHYON
The purpose of this study is to develop a dynamic risk assessment method that considers the inherent impact of a multi-unit system, using a simple plant model for a system with two units, and using an external event (Earthquake). A probabilistic risk assessment for a scenario of Loss of offsite power (LOOP) induced by an earthquake, was carried out considering the impact of multi-unit effects on accident progression. Furthermore, in order to evaluate the consideration of context in human reliability evaluation, which is a problem in the field of the PRA , A new model using Bayesian network and Fuzzy inference to evaluate the effect of environmental changes due to multi-unit effects on human error probability, was suggested.
Japan Society for the Promotion of Science, Grant-in-Aid for Early-Career Scientists, 18K14157
Industrial Property Rights
- 日本原子力学会国際委員会日韓原子力若手研究者交流事業運営小委員会・委員長
01 Apr. 2026 - Present
Planning etc
Academic society etc - 日本原子力学会リスク部会委員（研究・企画担当）
Apr. 2017 - Present
Planning etc
Academic society etc - NTHAS14（14th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety）LOC member & Student seminar Chair
2025 - 25 Nov. 2026
Planning etc, Others
Competition etc - 日本原子力学会国際委員会日韓原子力若手研究者交流事業運営小委員会・副委員長
Apr. 2017 - 31 Mar. 2026
Planning etc
Academic society etc - TPC member
01 Sep. 2024 - 31 Aug. 2025
Planning etc
Academic society etc
ASRAM2025 Organizing comittee - 幹事
31 May 2025
Academic research planning
Academic research
日本原子力学会「原子炉過酷事故に対する機構論的解析技術」研究専門委員会 - 日本原子力学会熱流動部会委員（広報担当）
01 Apr. 2023 - 31 Mar. 2025
Planning etc
Academic society etc - 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-12)
Nov. 2020 - Nov. 2022
Planning etc
Competition etc
LOC member
