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Proceedings Papers

Application of Global Importance Measures in RISMC for Dynamic Risk Assessment

Liye Ma, He Wang, Longcong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A065, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136084
https://doi.org/10.1115/ICONE31-136084
View Paper titled, Application of Global Importance Measures in RISMC for Dynamic Risk Assessment
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Topics: Risk, Risk assessment, Safety, Uncertainty, Nuclear power stations, Accidents, Alternating current (Electricity), Design, Engineering simulation, Failure
Proceedings Papers

The Development of the Fire PRA Model for Shimane Unit 2 Nuclear Power Plant

Kotaro Yoshizaki, Bumpei Fujioka, Daichi Shiota, Takahiro Usui, Hitoshi Nojima, Kenichi Kanda, Kazunobu Noriyasu
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134339
https://doi.org/10.1115/ICONE31-134339
View Paper titled, The Development of the Fire PRA Model for Shimane Unit 2 Nuclear Power Plant
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Topics: Fire, Nuclear power stations, Probabilistic risk assessment
Proceedings Papers

Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States

Takahiro Usui, Hiroki Nakamura, Kenichi Ihara, Yuki Hirai, Hitoshi Nojima, Satoshi Yoneda, Kenichi Kanda, Kazunobu Noriyasu, Daichi Shiota, Naoki Hirokawa
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134400
https://doi.org/10.1115/ICONE31-134400
View Paper titled, Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States
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Topics: Accidents, Airbags, Boiling water reactors, Design, Electricity (Physics), Engineering standards, Failure data, Fault tree analysis, Fukushima nuclear disaster, Japan, 2011, Human reliability analysis
Proceedings Papers

A Scoping Study on the Use of Direct Quantification of Fault Tree Using Monte Carlo Simulation in Seismic Probabilistic Risk Assessments

Kotaro Kubo, Keita Fujiwara, Yoichi Tanaka, Yuto Hakuta, Daisuke Arake, Tomoaki Uchiyama, Ken Muramatsu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88773
https://doi.org/10.1115/ICONE29-88773
View Paper titled, A Scoping Study on the Use of Direct Quantification of Fault Tree Using Monte Carlo Simulation in Seismic Probabilistic Risk Assessments
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Topics: Computation, Probabilistic risk assessment, Simulation
Proceedings Papers

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64117
https://doi.org/10.1115/ICONE28-64117
View Paper titled, RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions
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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64300
https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems

Yukihiko Okuda, Akemi Nishida, Michiya Sakai, Yuzo Shiogama, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A023, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64586
https://doi.org/10.1115/ICONE28-64586
View Paper titled, Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems
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Topics: Dynamic response, Piping systems, Pipes, Evaluation methods, Design, Mechanical behavior, Nuclear power stations, Probabilistic risk assessment, Structures
Proceedings Papers

Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants

Wu Guohua, Yuan Diping, Xiao Yiqing, Wang Jiaxin
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A023, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16191
https://doi.org/10.1115/ICONE2020-16191
View Paper titled, Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants
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Topics: Nuclear power stations, Chain, Explosions, Computer software, Failure, Probabilistic risk assessment
Proceedings Papers

MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant

Kenneth C. Wagner, David L. Y. Louie
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A045, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16584
https://doi.org/10.1115/ICONE2020-16584
View Paper titled, MELCOR Demonstration Analysis of Accident Scenarios at a Spent Nuclear Reprocessing Plant
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Topics: Accidents, Fire, Explosions, Radioisotopes, Aerosols, Model development, Nuclear power stations, Probabilistic risk assessment, Safety, Spent nuclear fuels
Proceedings Papers

Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases

Eishiro Higo, Shota Soga, Hiromichi Miura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A010, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16819
https://doi.org/10.1115/ICONE2020-16819
View Paper titled, Inter-Unit Common Cause Failure Analysis Based on Data From Intra-Unit Cases
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Topics: Failure, Failure analysis, Databases, Probability, Nuclear power stations, Performance, Probabilistic risk assessment
Proceedings Papers

Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment

Sai Zhang, Zhegang Ma
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16889
https://doi.org/10.1115/ICONE2020-16889
View Paper titled, Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment
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Topics: Probabilistic risk assessment, Reliability
Proceedings Papers

Dynamic PRA Based on System Codes Coupling for Passive Safety System in Integral Pressurized Water Reactor

Yi Mi, Akira Tokuhiro
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A034, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16558
https://doi.org/10.1115/ICONE2020-16558
View Paper titled, Dynamic PRA Based on System Codes Coupling for Passive Safety System in Integral Pressurized Water Reactor
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Topics: Pressurized water reactors, Safety, Reliability, Condensers (steam plant), Design, Failure, Flow (Dynamics), Friction, Gases, Heat
Proceedings Papers

Study on Shutdown Fire PRA for Nuclear Power Plant

Meiru Liu, Qingnan Zhao, Wei Deng, Jinyan Du, Lin Sun
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81272
https://doi.org/10.1115/ICONE26-81272
View Paper titled, Study on Shutdown Fire PRA for Nuclear Power Plant
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Topics: Fire, Nuclear power stations, Risk, China, Damage, Fire prevention, Fire risk, Ignition, Probabilistic risk assessment, Shorelines
Proceedings Papers

Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling

Hidemasa Yamano, Kenichi Naruto, Kenichi Kurisaka, Hiroyuki Nishino, Yasushi Okano
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81079
https://doi.org/10.1115/ICONE26-81079
View Paper titled, Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling
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Topics: Sodium fast reactors, Storage tanks, Vessels, Failure, Accidents, Sodium, Fuels, Damage, Dampers, Design
Proceedings Papers

Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes

Hideki Horie, Yutaka Takeuchi, Kenya Takiwaki, Fumie Sebe, Kazuo Kakiuchi, Hisaki Sato
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A034, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81923
https://doi.org/10.1115/ICONE26-81923
View Paper titled, Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes
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Topics: Accidents, Fuels, Oxidation, Cladding systems (Building), High temperature, Hydrogen, Nuclear power stations, Temperature, Chemical reactions, Damage
Proceedings Papers

Development and Application of Level 3 PSA for the UK ABWR Generic Design Assessment

Elizabeth Grindon, Neil Harman, Carmen Niculae, Ming Leang Ang, Hironobu Iwanami, Tomoharu Hashimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A044, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81469
https://doi.org/10.1115/ICONE26-81469
View Paper titled, Development and Application of Level 3 PSA for the UK ABWR Generic Design Assessment
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Topics: Design, Risk, Model development, Safety, Probabilistic risk assessment, Probabilistic safety assessment
Proceedings Papers

Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building

Byunghyun Choi, Akemi Nishida, Yinsheng Li, Ken Muramatsu, Tsuyoshi Takada
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82034
https://doi.org/10.1115/ICONE26-82034
View Paper titled, Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building
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Topics: Nuclear reactors, Uncertainty quantification, Uncertainty, Modeling, Accidents, Countermeasures, Design, Engineers, Finite element model, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

A Review of Multi-Unit Nuclear Power Plant Probabilistic Risk Assessment Research

Taotao Zhou, Mohammad Modarres, Enrique López Droguett
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81130
https://doi.org/10.1115/ICONE26-81130
View Paper titled, A Review of Multi-Unit Nuclear Power Plant Probabilistic Risk Assessment Research
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Topics: Nuclear power stations, Probabilistic risk assessment, Fukushima nuclear disaster, Japan, 2011, Modeling, Nuclear reactors, Risk, Workshops (Work spaces)
Proceedings Papers

The Development of the Advanced Method for the Source Term Evaluation Applicable to the Dynamic PRA

Koichi Nakamura, Sunghyon Jang, Akira Yamaguchi
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A045, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82523
https://doi.org/10.1115/ICONE26-82523
View Paper titled, The Development of the Advanced Method for the Source Term Evaluation Applicable to the Dynamic PRA
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Topics: Accidents, Containment, Evaluation methods, Nuclear fission, Nuclear power stations, Probabilistic risk assessment, Risk, Safety, Stress
Proceedings Papers

iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350

Tanaka Go, Sato Takashi, Komori Yuji, Matsumoto Keiji
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A025, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82552
https://doi.org/10.1115/ICONE26-82552
View Paper titled, iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350
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Topics: Optimization, Safety, Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Heat, Boiling water reactors, Condensers (steam plant), Cooling systems, Cylinders