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Proceedings Papers

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

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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

Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities

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Dan Lyu, Xiao-wei Yang, Yan Lu, Shi-jun Wang, Chun-yan Xu
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63354
https://doi.org/10.1115/ICONE28-63354
View Paper titled, Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities
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Topics: Failure, Failure data, Nuclear fuel cycle, Valves
Proceedings Papers

FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

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Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko
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, V001T04A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82048
https://doi.org/10.1115/ICONE26-82048
View Paper titled, FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty
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Topics: Nuclear power stations, Safety, Uncertainty, Computer software, Reliability, Failure mechanisms, Testing, Aerospace industry, Errors, Failure data
Proceedings Papers

Evaluation of Enhanced Risk Monitors for Use on Advanced Reactors

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Pradeep Ramuhalli, Arun Veeramany, Christopher A. Bonebrake, William J. Ivans, Jr., Garill A. Coles, Evelyn H. Hirt
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A003, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60040
https://doi.org/10.1115/ICONE24-60040
View Paper titled, Evaluation of Enhanced Risk Monitors for Use on Advanced Reactors
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Topics: Risk, Failure, Maintenance, Safety, Control algorithms, Damage, Decision making, Design, Economics , Failure data
Proceedings Papers

Method for Establishing Risk Significance of Procedural Actions for Pre-Initiating Events for Operating Nuclear Power Plants

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C. R. Grantom, Pamela Nelson
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 155-160, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54656
https://doi.org/10.1115/ICONE20-POWER2012-54656
View Paper titled, Method for Establishing Risk Significance of Procedural Actions for Pre-Initiating Events for Operating Nuclear Power Plants
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Topics: Errors, Human reliability analysis, Nuclear power stations, Risk, Failure, Databases, Failure data, Maintenance, Probabilistic risk assessment, Risk analysis
Proceedings Papers

Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions

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Lin Li, Bo Zhao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 431-445, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29007
https://doi.org/10.1115/ICONE18-29007
View Paper titled, Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions
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Topics: Nuclear power stations, Probabilistic safety assessment, Risk, Human reliability analysis, Computer software, Damage, Design, Failure data, Safety, Systems analysis
Proceedings Papers

Initial Events Assessment of Auxiliary Building for Internal Flooding PSA

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Renzong Chen
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 81-99, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29053
https://doi.org/10.1115/ICONE18-29053
View Paper titled, Initial Events Assessment of Auxiliary Building for Internal Flooding PSA
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Topics: Floods, Failure data, Failure mechanisms, Hazards, Nuclear power stations, Piping systems, Pressurized water reactors
Proceedings Papers

Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and Information

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Tadahisa Nagata, Ken-ichiro Sugiyama
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 217-224, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75914
https://doi.org/10.1115/ICONE17-75914
View Paper titled, Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and Information
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Topics: Nuclear power stations, Performance evaluation, Failure, Maintenance, Databases, Design, Failure data, Plant design, Plant engineering (Facilities), Weibull distribution
Proceedings Papers

A Point Process Model for Piping Failure Frequency Analysis Using OPDE Data

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X.-X. Yuan, M. D. Pandey, J. Riznic
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 433-441, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48078
https://doi.org/10.1115/ICONE16-48078
View Paper titled, A Point Process Model for Piping Failure Frequency Analysis Using OPDE Data
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Topics: Failure, Pipes, Databases, Failure data, Nuclear power stations, Probabilistic risk assessment, Risk-informed in-service inspection
Proceedings Papers

Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance

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E. Kevin Doyle
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 1-9, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22011
https://doi.org/10.1115/ICONE10-22011
View Paper titled, Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance
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Topics: Complex systems, Containment, Design, Engineers, Errors, Failure, Failure data, Maintenance, Nuclear power, Nuclear power plant maintenance
Proceedings Papers

Stochastic Maintenance Optimization at Candu Power Plants

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E. Kevin Doyle, T. Duschesne, C. G. Lee, D. I. Cho
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 33-42, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49074
https://doi.org/10.1115/ICONE12-49074
View Paper titled, Stochastic Maintenance Optimization at Candu Power Plants
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Topics: Maintenance, Optimization, Power stations, Complex systems, Construction, Energy generation, Failure, Failure data, Statistical analysis, Statistics
Proceedings Papers

A Reliability Study of the Diesel Generator of the HANARO Research Reactor

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Hyungkyoo Kim, Hoansung Jung, Jongsup Wu, Byungjin Jun
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 29-32, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49042
https://doi.org/10.1115/ICONE12-49042
View Paper titled, A Reliability Study of the Diesel Generator of the HANARO Research Reactor
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Topics: Diesel generators, Reliability, Emergencies, Failure, Probability, Failure data, Nuclear reactors, Ventilation, Water supply
Proceedings Papers

The OECD Pipe Failure Data Exchange Project: Data Validation on Canadian Plants

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Alexandre Colligan, Robert Lojk, Jovica Riznic
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 65-70, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49273
https://doi.org/10.1115/ICONE12-49273
View Paper titled, The OECD Pipe Failure Data Exchange Project: Data Validation on Canadian Plants
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Topics: Failure data, Pipes, Failure, Nuclear power, Nuclear power stations
Proceedings Papers

OECD Pipe Failure Data Exchange Project (OPDE): 2003 Status Report

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Bengt Lydell, Eric Mathet, Karen Gott
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 23-27, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49217
https://doi.org/10.1115/ICONE12-49217
View Paper titled, OECD Pipe Failure Data Exchange Project (OPDE): 2003 Status Report
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Topics: Failure data, Pipes, Failure, Reliability, Nuclear power, Safety
Proceedings Papers

The OECD Pipe Failure Data Exchange Project: Validation of Canadian Data

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Tom Viglaski, Andrei Blahoianu, Bengt Lydell, Jovica Riznic
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 389-400, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89176
https://doi.org/10.1115/ICONE14-89176
View Paper titled, The OECD Pipe Failure Data Exchange Project: Validation of Canadian Data
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Topics: Failure data, Pipes, Failure, Databases, Nondestructive evaluation, Feedback, Industrial research, In-service inspection, Leak-before-break, Nuclear power