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Proceedings Papers

Development of Guideline on Seismic Fragility Evaluation for Aged Piping

Yoshihito Yamaguchi, Jinya Katsuyama, Koichi Masaki, Yinsheng Li

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A028, July 13–15, 2021

Paper No: PVP2021-61509

DOI: https://doi.org/10.1115/PVP2021-61509

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Topics: Fracture mechanics, Pipes, Nuclear power stations, Piping systems, Probabilistic risk assessment, Accidents, Damage, Earthquake risk, Fracture (Materials), Safety

Proceedings Papers

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Hitoshi Muta, Yasuki Ohtori, Osamu Furuya, Satoshi Fujita

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A021, July 13–15, 2021

Paper No: PVP2021-61742

DOI: https://doi.org/10.1115/PVP2021-61742

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Topics: Nuclear power stations, Reliability, Safety, Accidents, Design, Countermeasures, Fukushima nuclear disaster, Japan, 2011, Regulations, Defense industry, Earthquake risk

Proceedings Papers

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Kisaburo Azuma, Yoshihito Yamaguchi, Yinsheng Li

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A063, July 13–15, 2021

Paper No: PVP2021-62233

DOI: https://doi.org/10.1115/PVP2021-62233

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Topics: Fracture mechanics, Pipes, Stainless steel, Inspection, Maintenance, Stress corrosion cracking, Failure, Probabilistic risk assessment, Probability, Design

Proceedings Papers

Probabilistic Risk Assessment of Aging Layered Pressure Vessels

D. S. Riha, M. L. Kirby, J. W. Cardinal, L. C. Domyancic, J. M. McFarland, F. W. Brust

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A046, July 14–19, 2019

Paper No: PVP2019-93720

DOI: https://doi.org/10.1115/PVP2019-93720

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Topics: Fitness-for-service, Pressure vessels, Probabilistic risk assessment, Risk assessment, Shells, Stress

Proceedings Papers

Contribution to Safety Enhancement for BDBE in Structure and Material Fields

Naoto Kasahara, Takuya Sato, Andrei Blahoianu

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A047, July 15–20, 2018

Paper No: PVP2018-84353

DOI: https://doi.org/10.1115/PVP2018-84353

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Topics: Safety, Accidents, Failure mechanisms, Design, Failure, Fracture (Materials), Fracture (Process), Fukushima nuclear disaster, Japan, 2011, Probabilistic risk assessment, Risk

Proceedings Papers

Crack Growth Prediction for Cracked Dissimilar Metal Weld Joint in Pipe Under Large Seismic Cyclic Loading

Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A084, July 15–20, 2018

Paper No: PVP2018-85022

DOI: https://doi.org/10.1115/PVP2018-85022

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Topics: Fracture (Materials), Metals, Pipes, Nuclear power stations, Welded joints, Evaluation methods, Alloys, Nickel, Seismic hazard assessment, Stainless steel

Proceedings Papers

Difference of Strength Evaluation Approach Between for DBE and for BDBE

Naoto Kasahara, Takuya Sato

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A005, July 16–20, 2017

Paper No: PVP2017-65478

DOI: https://doi.org/10.1115/PVP2017-65478

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Topics: Accident management, Accidents, Countermeasures, Design, Elastic analysis, Failure, Failure mechanisms, Fukushima nuclear disaster, Japan, 2011, Inelastic analysis, Probabilistic risk assessment

Proceedings Papers

Resilience of Masonry Systems in Nuclear Power Plants Under Blast Risk

Manuel Campidelli, Wael W. El-Dakhakhni, Michael J. Tait, Waleed Mekky

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A020, July 16–20, 2017

Paper No: PVP2017-65301

DOI: https://doi.org/10.1115/PVP2017-65301

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Topics: Masonry, Nuclear power stations, Resilience, Risk, Design, Explosives, Hazards, Explosions, Geometry, Maintenance

Proceedings Papers

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 6 — Proposal of New Type of Hysteresis Model for Ultimate Behavior

Tsuyoshi Fukasawa, Shigeki Okamura, Tomohiko Yamamoto, Tomoyoshi Watakabe

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A044, July 16–20, 2017

Paper No: PVP2017-65557

DOI: https://doi.org/10.1115/PVP2017-65557

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Topics: Bearings, Rubber, Sodium fast reactors, Design, Differential equations, Deformation, Earthquakes, Probabilistic risk assessment, Risk

Proceedings Papers

Thoughts on Improving Confidence in Probabilistic Fracture Mechanics Analyses

D. Rudland, M. Kirk, P. Raynaud

Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A053, July 17–21, 2016

Paper No: PVP2016-63771

DOI: https://doi.org/10.1115/PVP2016-63771

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Topics: Fracture mechanics, Uncertainty, Safety, Fracture (Materials), Fracture (Process), ASME Boiler and Pressure Vessel Code, Decision making, Design, Engineering standards, Probabilistic risk assessment

Proceedings Papers

Failure Probability Analysis of Aged Piping Using Probabilistic Fracture Mechanics Methodology Considering Seismic Loads

Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A054, July 17–21, 2016

Paper No: PVP2016-63801

DOI: https://doi.org/10.1115/PVP2016-63801

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Topics: Failure, Fracture mechanics, Pipes, Probability, Stress, Piping systems, Earthquakes, Fracture (Materials), In-service inspection, Nuclear power

Proceedings Papers

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 3 — Ultimate Properties of a Half Scale Thick Rubber Bearings Based on Breaking Test

Tsuyoshi Fukasawa, Shigeki Okamura, Tomohiko Yamamoto, Nobuchika Kawasaki, Tsutomu Hirotani, Eriko Moriizumi, Yu Sakurai, Nobuo Masaki

Proc. ASME. PVP2016, Volume 8: Seismic Engineering, V008T08A035, July 17–21, 2016

Paper No: PVP2016-63397

DOI: https://doi.org/10.1115/PVP2016-63397

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Topics: Bearings, Rubber, Sodium fast reactors, Stress, Damping, Knudsen number, Nuclear power stations, Probabilistic risk assessment, Safety, Stiffness

Proceedings Papers

Fatigue Failure Evaluation Method and Fragility Curve Using Energy

Keisuke Minagawa, Satoshi Fujita, Shigeki Okamura

Proc. ASME. PVP2015, Volume 8: Seismic Engineering, V008T08A024, July 19–23, 2015

Paper No: PVP2015-45486

DOI: https://doi.org/10.1115/PVP2015-45486

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Topics: Evaluation methods, Fatigue failure, Damage, Earthquakes, Earthquake resistant design, Mechanical structures, Probabilistic risk assessment

Proceedings Papers

Response Analysis of a Seismic Isolated Structure Considering a Probabilistic Approach

Naoki Akamatsu, Satoshi Fujita, Keisuke Minagawa

Proc. ASME. PVP2014, Volume 8: Seismic Engineering, V008T08A029, July 20–24, 2014

Paper No: PVP2014-28596

DOI: https://doi.org/10.1115/PVP2014-28596

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Topics: Accidents, Bearings, Earthquake resistant design, Earthquakes, Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Probabilistic risk assessment, Risk, Rubber

Proceedings Papers

Seismic Probabilistic Risk Assessment of Nuclear Power Plants Using Response-Based Fragility Curves

Ying-Hsiu Shen, Yin-Nan Huang, Ching-Ching Yu

Proc. ASME. PVP2014, Volume 8: Seismic Engineering, V008T08A030, July 20–24, 2014

Paper No: PVP2014-29116

DOI: https://doi.org/10.1115/PVP2014-29116

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Topics: Nuclear power stations, Probabilistic risk assessment, Earthquake risk, Algebra, Damage, Accidents, Radiation (Physics), Risk, Simulation, Statistical distributions

Proceedings Papers

Research Plan on Failure Modes by Extreme Loadings Under Design Extension Conditions

Naoto Kasahara, Izumi Nakamura, Hideo Machida, Hitoshi Nakamura

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A041, July 20–24, 2014

Paper No: PVP2014-28349

DOI: https://doi.org/10.1115/PVP2014-28349

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Topics: Design, Failure mechanisms, Accidents, Earthquakes, High pressure (Physics), Accident management, Collapse, Countermeasures, Ductile fracture, Failure

Proceedings Papers

Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events

Hsoung-Wei Chou, Chin-Cheng Huang

Proc. ASME. PVP2014, Volume 7: Operations, Applications and Components, V007T07A019, July 20–24, 2014

Paper No: PVP2014-28350

DOI: https://doi.org/10.1115/PVP2014-28350

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Topics: Pressure vessels, Pressurized water reactors, Reliability, Thermal shock, Reactor vessels, Cracking (Materials), Failure, Fracture (Process), Nuclear power stations, Fracture mechanics

Proceedings Papers

Degradation Susceptibility Metrics as the Bases for Bayesian Reliability Models of Aging Passive Components and Long-Term Reactor Risk

Stephen D. Unwin, Peter P. Lowry, Michael Y. Toyooka, Benjamin E. Ford

Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 1069-1075, July 17–21, 2011

Paper No: PVP2011-58073

DOI: https://doi.org/10.1115/PVP2011-58073

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Topics: Reliability, Risk, Materials degradation, Design, Failure, Materials management, Probabilistic risk assessment

Proceedings Papers

Component Degradation Susceptibilities as the Bases for Modeling Reactor Aging Risk

Stephen D. Unwin, Peter P. Lowry, Michael Y. Toyooka

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1151-1155, July 18–22, 2010

Paper No: PVP2010-25750

DOI: https://doi.org/10.1115/PVP2010-25750

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Topics: Modeling, Risk, Failure, Carbon, Climate, Materials degradation, Materials research, Nuclear power stations, Physics, Probabilistic risk assessment

Proceedings Papers

Overview of Implementation of Probabilistic-Risk-Assessment-Based Seismic Margin Analyses in Design Certification and Combined License Applications

Jim Xu

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 8, 231-237, July 18–22, 2010

Paper No: PVP2010-25160

DOI: https://doi.org/10.1115/PVP2010-25160

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Topics: Design, Licensing, Risk, Safety, Earthquake risk, Failure, Light water reactors, Nuclear power stations, Accidents, Containment

NARROW

Development of Guideline on Seismic Fragility Evaluation for Aged Piping

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Probabilistic Risk Assessment of Aging Layered Pressure Vessels

Contribution to Safety Enhancement for BDBE in Structure and Material Fields

Crack Growth Prediction for Cracked Dissimilar Metal Weld Joint in Pipe Under Large Seismic Cyclic Loading

Difference of Strength Evaluation Approach Between for DBE and for BDBE

Resilience of Masonry Systems in Nuclear Power Plants Under Blast Risk

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 6 — Proposal of New Type of Hysteresis Model for Ultimate Behavior

Thoughts on Improving Confidence in Probabilistic Fracture Mechanics Analyses

Failure Probability Analysis of Aged Piping Using Probabilistic Fracture Mechanics Methodology Considering Seismic Loads

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 3 — Ultimate Properties of a Half Scale Thick Rubber Bearings Based on Breaking Test

Fatigue Failure Evaluation Method and Fragility Curve Using Energy

Response Analysis of a Seismic Isolated Structure Considering a Probabilistic Approach

Seismic Probabilistic Risk Assessment of Nuclear Power Plants Using Response-Based Fragility Curves

Research Plan on Failure Modes by Extreme Loadings Under Design Extension Conditions

Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events

Degradation Susceptibility Metrics as the Bases for Bayesian Reliability Models of Aging Passive Components and Long-Term Reactor Risk

Component Degradation Susceptibilities as the Bases for Modeling Reactor Aging Risk

Overview of Implementation of Probabilistic-Risk-Assessment-Based Seismic Margin Analyses in Design Certification and Combined License Applications

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