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Proceedings Papers

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

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

Paper No: ICONE28-63354

DOI: https://doi.org/10.1115/ICONE28-63354

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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

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

Paper No: ICONE26-82048

DOI: https://doi.org/10.1115/ICONE26-82048

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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

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

Paper No: ICONE24-60040

DOI: https://doi.org/10.1115/ICONE24-60040

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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

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

Paper No: ICONE20-POWER2012-54656

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54656

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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

Lin Li, Bo Zhao

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 431-445, May 17–21, 2010

Paper No: ICONE18-29007

DOI: https://doi.org/10.1115/ICONE18-29007

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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

Renzong Chen

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 81-99, May 17–21, 2010

Paper No: ICONE18-29053

DOI: https://doi.org/10.1115/ICONE18-29053

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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

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

Paper No: ICONE17-75914

DOI: https://doi.org/10.1115/ICONE17-75914

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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

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

Paper No: ICONE16-48078

DOI: https://doi.org/10.1115/ICONE16-48078

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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

E. Kevin Doyle

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 1-9, April 14–18, 2002

Paper No: ICONE10-22011

DOI: https://doi.org/10.1115/ICONE10-22011

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Topics: Complex systems, Containment, Design, Engineers, Errors, Failure, Failure data, Maintenance, Nuclear power, Nuclear power plant maintenance

Proceedings Papers

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

Bengt Lydell, Eric Mathet, Karen Gott

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 23-27, April 25–29, 2004

Paper No: ICONE12-49217

DOI: https://doi.org/10.1115/ICONE12-49217

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Topics: Failure data, Pipes, Failure, Reliability, Nuclear power, Safety

Proceedings Papers

Stochastic Maintenance Optimization at Candu Power Plants

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

Paper No: ICONE12-49074

DOI: https://doi.org/10.1115/ICONE12-49074

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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

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

Paper No: ICONE12-49042

DOI: https://doi.org/10.1115/ICONE12-49042

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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

Alexandre Colligan, Robert Lojk, Jovica Riznic

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 65-70, April 25–29, 2004

Paper No: ICONE12-49273

DOI: https://doi.org/10.1115/ICONE12-49273

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Topics: Failure data, Pipes, Failure, Nuclear power, Nuclear power stations

Proceedings Papers

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

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

Paper No: ICONE14-89176

DOI: https://doi.org/10.1115/ICONE14-89176

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Topics: Failure data, Pipes, Failure, Databases, Nondestructive evaluation, Feedback, Industrial research, In-service inspection, Leak-before-break, Nuclear power

NARROW

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

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

Evaluation of Enhanced Risk Monitors for Use on Advanced Reactors

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

Probabilistic Safety Assessment to the 1000 MWe NPP During Shutdown Conditions

Initial Events Assessment of Auxiliary Building for Internal Flooding PSA

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

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

Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance

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

Stochastic Maintenance Optimization at Candu Power Plants

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

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

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

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