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Proceedings Papers

Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Yasuto Nagoshi, Kai Lu, Jinya Katsuyama

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A057, July 13–15, 2021

Paper No: PVP2021-61725

DOI: https://doi.org/10.1115/PVP2021-61725

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Topics: Cladding systems (Building), Fracture (Materials), Fracture toughness, Reactor vessels, Steel

Proceedings Papers

Modeling Dependencies in Engineering Design

Kai-Lu Wang, Yan Jin

Proc. ASME. DETC99, Volume 3: 11th International Conference on Design Theory and Methodology, 389-398, September 12–16, 1999

Paper No: DETC99/DTM-8778

DOI: https://doi.org/10.1115/DETC99/DTM-8778

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Topics: Design, Engineering design, Modeling, Computers, Conceptual design, Concurrent engineering, Engineering design processes, Engineering research, Process design

Proceedings Papers

Managing Dependencies for Collaborative Design

Kai-Lu Wang, Yan Jin

Proc. ASME. IDETC-CIE2000, Volume 4: 12th International Conference on Design Theory and Methodology, 93-102, September 10–13, 2000

Paper No: DETC2000/DTM-14552

DOI: https://doi.org/10.1115/DETC2000/DTM-14552

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Topics: Design

Journal Articles

Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe, Yinsheng Li

J. Pressure Vessel Technol. June 2021, 143(3): 031704.

Paper No: PVT-20-1128

DOI: https://doi.org/10.1115/1.4049048

Published Online: November 18, 2020

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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Pressurized water reactors, Probability, Reactor vessels, Water temperature

Proceedings Papers

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Kai Lu, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A062, August 3, 2020

Paper No: PVP2020-21421

DOI: https://doi.org/10.1115/PVP2020-21421

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Topics: Boiling water reactors, Fracture mechanics, Reactor vessels, Transients (Dynamics), Fracture (Materials), Pressurized water reactors, Surface cracks, Computational methods, Embrittlement, Irradiation (Radiation exposure)

Proceedings Papers

Improved Bayesian Update Method on Flaw Distributions Reflecting Non-Destructive Inspection Result

Jinya Katsuyama, Yuhei Miyamoto, Kai Lu, Akihiro Mano, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A064, August 3, 2020

Paper No: PVP2020-21430

DOI: https://doi.org/10.1115/PVP2020-21430

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Topics: Fracture mechanics, Nondestructive evaluation, Reactor vessels

Journal Articles

Application of Probabilistic Fracture Mechanics to Reactor Pressure Vessel Using PASCAL4 Code

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura

J. Pressure Vessel Technol. April 2021, 143(2): 021505.

Paper No: PVT-20-1061

DOI: https://doi.org/10.1115/1.4048103

Published Online: October 5, 2020

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Topics: Embrittlement, Failure, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutron flux, Neutrons, Nondestructive evaluation, Reactor vessels, Transients (Dynamics)

Journal Articles

Plasticity Correction on Stress Intensity Factor Evaluation for Underclad Cracks in Reactor Pressure Vessels

Kai Lu, Jinya Katsuyama, Yinsheng Li

J. Pressure Vessel Technol. October 2020, 142(5): 051501.

Paper No: PVT-18-1079

DOI: https://doi.org/10.1115/1.4046977

Published Online: May 22, 2020

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Topics: Finite element analysis, Fracture (Materials), Plasticity, Reactor vessels, Stress, Cladding systems (Building)

Journal Articles

Improvements on Evaluation Functions of a Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessels

Kai Lu, Jinya Katsuyama, Yinsheng Li

J. Pressure Vessel Technol. April 2020, 142(2): 021208.

Paper No: PVT-19-1083

DOI: https://doi.org/10.1115/1.4045512

Published Online: December 11, 2019

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Topics: Fracture (Materials), Fracture mechanics, Failure

Proceedings Papers

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A057, July 14–19, 2019

Paper No: PVP2019-93935

DOI: https://doi.org/10.1115/PVP2019-93935

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Topics: Fracture mechanics, Reactor vessels, Failure, Neutrons, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Light water reactors, Nondestructive evaluation, Nuclear power

Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019

Paper No: PVP2019-93967

DOI: https://doi.org/10.1115/PVP2019-93967

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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors

Proceedings Papers

Development of Crack Evaluation Models for Probabilistic Fracture Mechanics Analyses of Japanese Reactor Pressure Vessels

Kai Lu, Koichi Masaki, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A057, July 15–20, 2018

Paper No: PVP2018-84965

DOI: https://doi.org/10.1115/PVP2018-84965

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Topics: Fracture (Materials), Fracture mechanics, Reactor vessels, Failure, Crack propagation, Embrittlement, Finite element analysis, Irradiation (Radiation exposure), Neutrons, Nuclear power

Proceedings Papers

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL Version 4 for Reactor Pressure Vessels

Kai Lu, Koichi Masaki, Jinya Katsuyama, Yinsheng Li, Shumpei Uno

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A003, July 15–20, 2018

Paper No: PVP2018-84964

DOI: https://doi.org/10.1115/PVP2018-84964

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Topics: Fracture mechanics, Reactor vessels, Embrittlement, Failure, Irradiation (Radiation exposure), Stress, Computational methods, Light water reactors, Neutrons, Nuclear power

Journal Articles

Development of Stress Intensity Factors for Subsurface Flaws in Plates Subjected to Polynomial Stress Distributions

Kai Lu, Mano Akihiro, Jinya Katsuyama, Yinsheng Li, Fuminori Iwamatsu

J. Pressure Vessel Technol. June 2018, 140(3): 031201.

Paper No: PVT-17-1095

DOI: https://doi.org/10.1115/1.4039125

Published Online: April 18, 2018

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Topics: Finite element analysis, Polynomials, Stress, Flat plates, Stress concentration

Proceedings Papers

Probabilistic Fracture Mechanics Analysis Models for Japanese Reactor Pressure Vessels

Kai Lu, Jinya Katsuyama, Shumpei Uno, Yinsheng Li

Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A006, July 16–20, 2017

Paper No: PVP2017-66003

DOI: https://doi.org/10.1115/PVP2017-66003

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Topics: Fracture mechanics, Reactor vessels, Failure, Evaluation methods, Fracture (Materials), Nuclear power, Probability, Stress concentration, Welding

Journal Articles

Remaining Fatigue Lives of Similar Surface Flaws in Accordance With Combination Rules

Kai Lu, Yinsheng Li, Kunio Hasegawa, Valery Lacroix

J. Pressure Vessel Technol. April 2017, 139(2): 021407.

Paper No: PVT-16-1086

DOI: https://doi.org/10.1115/1.4035317

Published Online: January 11, 2017

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Topics: Fatigue, ASME Standards, Finite element methods

Proceedings Papers

Stress Intensity Factor Solutions for Subsurface Flaws in Plates Subjected to Polynomial Stress Distributions

Kai Lu, Jinya Katsuyama, Yinsheng Li, Fuminori Iwamatsu

Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A013, July 17–21, 2016

Paper No: PVP2016-63479

DOI: https://doi.org/10.1115/PVP2016-63479

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Topics: Plates (structures), Polynomials, Stress, Engineering systems and industry applications, Finite element analysis, Wall thickness

Proceedings Papers

Fatigue Lives of Multiple Flaws in Accordance With Combination Rule

Kai Lu, Yinsheng Li, Kunio Hasegawa, Valery Lacroix

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A009, July 17–21, 2016

Paper No: PVP2016-63483

DOI: https://doi.org/10.1115/PVP2016-63483

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Topics: Fatigue, Finite element methods, ASME Standards, Fitness-for-service, Pipes, Structural elements (Construction), Tension

Proceedings Papers

Plasticity Correction on the Stress Intensity Factor Evaluation for Underclad Cracks Under Pressurized Thermal Shock Events

Kai Lu, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A004, July 17–21, 2016

Paper No: PVP2016-63486

DOI: https://doi.org/10.1115/PVP2016-63486

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Topics: Fracture (Materials), Plasticity, Stress, Thermal shock, Cladding systems (Building), Finite element analysis, Corrosion protection, Geometry, Overlays (Materials engineering), Reactor vessels

Proceedings Papers

Applicability of a Deterministic Approach to Transfer the Fracture Toughness J c Between Different Specimen Thicknesses

Toshiyuki Meshii, Kai Lu

Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A059, July 19–23, 2015

Paper No: PVP2015-45071

DOI: https://doi.org/10.1115/PVP2015-45071

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Topics: Fracture toughness, Failure, Steel, ASTM International, Brittleness, Databases, Electromagnetic scattering, Phase transition temperature, Reactor vessels, Stress

Journal citation

NARROW

Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel

Modeling Dependencies in Engineering Design

Managing Dependencies for Collaborative Design

Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Improved Bayesian Update Method on Flaw Distributions Reflecting Non-Destructive Inspection Result

Application of Probabilistic Fracture Mechanics to Reactor Pressure Vessel Using PASCAL4 Code

Plasticity Correction on Stress Intensity Factor Evaluation for Underclad Cracks in Reactor Pressure Vessels

Improvements on Evaluation Functions of a Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessels

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Development of Crack Evaluation Models for Probabilistic Fracture Mechanics Analyses of Japanese Reactor Pressure Vessels

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL Version 4 for Reactor Pressure Vessels

Development of Stress Intensity Factors for Subsurface Flaws in Plates Subjected to Polynomial Stress Distributions

Probabilistic Fracture Mechanics Analysis Models for Japanese Reactor Pressure Vessels

Remaining Fatigue Lives of Similar Surface Flaws in Accordance With Combination Rules

Stress Intensity Factor Solutions for Subsurface Flaws in Plates Subjected to Polynomial Stress Distributions

Fatigue Lives of Multiple Flaws in Accordance With Combination Rule

Plasticity Correction on the Stress Intensity Factor Evaluation for Underclad Cracks Under Pressurized Thermal Shock Events

Applicability of a Deterministic Approach to Transfer the Fracture Toughness J c Between Different Specimen Thicknesses

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