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Hiroyuki Nishino

Observed name: Hiroyuki NISHINO
Observed institution: Japan Atomic Energy Agency
OpenAlex ID: A5002530359
Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor
2016 · Hidemasa Yamano, Hiroyuki Nishino, et al. · Nuclear Engineering and Design · 6
Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors
2017 · Hidemasa Yamano, Hiroyuki Nishino, et al. · ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems Part B Mechanical Engineering · 4
Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors
2017 · Hidemasa Yamano, Hiroyuki Nishino, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
Safety design approach for external events in Japan sodium-cooled fast reactor
2012 · Hidemasa Yamano, S. Kubo, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Development of probabilistic risk assessment methodology against strong wind for sodium-cooled fast reactors
2023 · Hiroyuki NISHINO, Hidemasa YAMANO, et al. · Mechanical Engineering Journal · 1
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Effectiveness Evaluation Methodology of the Measures for Improving Resilience of Nuclear Structures Against Excessive Earthquake
2023 · Kenichi Kurisaka, Hiroyuki Nishino, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Development of a probabilistic risk assessment methodology against a combination hazard of strong wind and rainfall for sodium-cooled fast reactors
2018 · Hidemasa YAMANO, Hiroyuki NISHINO, et al. · Mechanical Engineering Journal · 1
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Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors
2017 · Hiroyuki Nishino, Hidemasa Yamano, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Research and development of probabilistic risk assessment methodology for combination event of low temperature and snow
2016 · Hiroyuki NISHINO, Hidemasa YAMANO, et al. · Transactions of the JSME (in Japanese) · 1
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Development of extreme rainfall PRA methodology for sodium-cooled fast reactor
2016 · Hiroyuki Nishino, Kenichi Kurisaka, et al. · 1
Research and Development of Probabilistic Risk Assessment Methodology for Combination Event of Low Temperature and Snow
2016 · Hiroyuki Nishino, Hidemasa Yamano, et al. · Doryoku, Enerugi Gijutsu Shinpojiumu koen ronbunshu/Doryoku, enerugi gijutsu no saizensen koen ronbunshu · 1
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Icone23-1003 Development of Risk Assessment Methodology of Decay Heat Removal Function Against External Hazards for Sodium-cooled Fast Reactors : (1) Project Overview and Margin Assessment Methodology Against Snow
2015 · Hidemasa Yamano, Hiroyuki Nishino, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
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Tsunami PRA for Japan sodium-cooled fast reactor
2014 · Hiroyuki Nishino, Kenichi Kurisaka, et al. · 1
Reduction of accident occurrence frequencies by taking safety measures for defense-in-depth level 4 in a sodium-cooled fast reactor
2023 · Hiroyuki NISHINO, Kenichi KURISAKA, et al. · Mechanical Engineering Journal
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Internal Event Level-1 Pra for Sodium-cooled Fast Reactor Considering Safety Measures of Defense-in-depth Level 1 to 4
2023 · Hiroyuki Nishino, Kenichi Kurisaka, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Fundamental Study on Failure Evaluation Method of Integrated Vibration Energy for Component
2021 · Shigeki OKAMURA, Takahiro KINOSHITA, et al. · Doryoku, Enerugi Gijutsu Shinpojiumu koen ronbunshu/Doryoku, enerugi gijutsu no saizensen koen ronbunshu
Study on Seismic Analysis Method of Fast Reactor Plant with Seismic Isolation System
2020 · Shigeki OKAMURA, Takahiro KINOSHITA, et al. · The Proceedings of Mechanical Engineering Congress Japan
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Level 1 PRA for External Vessel Storage Tank in Whole Core Refueling in Advanced Loop-Type Sodium-Cooled Fast Reactor
2019 · Hidemasa YAMANO, Kenichi NARUTO, et al. · The Proceedings of Mechanical Engineering Congress Japan
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Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling
2018 · Hidemasa Yamano, Kenichi Naruto, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Study on Effectiveness Evaluations of Countermeasures against Severe Accidents in Fast Reactor
2018 · Hiroyuki Nishino · Atomic Energy Society of Japan
Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors
2018 · Hiroyuki NISHINO, Hidemasa YAMANO, et al. · Mechanical Engineering Journal
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Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards
2016 · Hiroyuki Nishino · Atomic Energy Society of Japan
Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology
2016 · Hidemasa Yamano, Hiroyuki Nishino, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Development of Risk Assessment Methodology Against External Hazards for Sodium-Cooled Fast Reactors
2016 · Hidemasa Yamano, Hiroyuki Nishino, et al. · Springer eBooks
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Icone23-1112 Development of Risk Assessment Methodology of Decay Heat Removal Function Against External Hazards for Sodium-cooled Fast Reactors : (2) Probabilistic Risk Assessment Methodology Against Strong Wind
2015 · Hiroyuki Nishino, Kenichi Kurisaka, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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Works count: 26
Citation count: 23
H-index: 2
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