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Proceedings Papers

Development of Guideline on Seismic Fragility Evaluation for Aged Piping

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Yoshihito Yamaguchi, Jinya Katsuyama, Koichi Masaki, Yinsheng Li
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A028, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61509
https://doi.org/10.1115/PVP2021-61509
View Paper titled, Development of Guideline on Seismic Fragility Evaluation for Aged Piping
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Topics: Fracture mechanics, Pipes, Nuclear power stations, Piping systems, Probabilistic risk assessment, Accidents, Damage, Earthquake risk, Fracture (Materials), Safety
Journal Articles

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

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Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2021, 143(4): 041501.
Paper No: PVT-18-1049
https://doi.org/10.1115/1.4049693
Published Online: February 11, 2021
View Articletitled, Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutrons, Probability, Reactor vessels, Transients (Dynamics), Fracture (Process), Structural elements (Construction)
Journal Articles

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

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Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2021, 143(3): 031704.
Paper No: PVT-20-1128
https://doi.org/10.1115/1.4049048
Published Online: November 18, 2020
View Articletitled, Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Pressurized water reactors, Probability, Reactor vessels, Water temperature
Proceedings Papers

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

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Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93967
https://doi.org/10.1115/PVP2019-93967
View Paper titled, Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV
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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

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Kai Lu, Koichi Masaki, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A057, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84965
https://doi.org/10.1115/PVP2018-84965
View Paper titled, Development of Crack Evaluation Models for Probabilistic Fracture Mechanics Analyses of Japanese Reactor Pressure Vessels
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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

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Kai Lu, Koichi Masaki, Jinya Katsuyama, Yinsheng Li, Shumpei Uno
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A003, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84964
https://doi.org/10.1115/PVP2018-84964
View Paper titled, Development of Probabilistic Fracture Mechanics Analysis Code PASCAL Version 4 for Reactor Pressure Vessels
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Topics: Fracture mechanics, Reactor vessels, Embrittlement, Failure, Irradiation (Radiation exposure), Stress, Computational methods, Light water reactors, Neutrons, Nuclear power
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses

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Yinsheng Li, Shumpei Uno, Koichi Masaki, Jinya Katsuyama, Terry Dickson, Mark Kirk
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A075, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84963
https://doi.org/10.1115/PVP2018-84963
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses
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Topics: Fracture mechanics, Failure, Probability, Embrittlement, Irradiation (Radiation exposure), Neutrons, Nuclear power, Reactor vessels, Thermal shock
Proceedings Papers

Verification Methodology and Results of Probabilistic Fracture Mechanics Code PASCAL

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Koichi Masaki, Yuhei Miyamoto, Kazuya Osakabe, Shumpei Uno, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A005, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65950
https://doi.org/10.1115/PVP2017-65950
View Paper titled, Verification Methodology and Results of Probabilistic Fracture Mechanics Code PASCAL
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Topics: Fracture mechanics, Failure, Nuclear power, Reactor vessels, Thermal shock
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

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Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66468
https://doi.org/10.1115/ICONE25-66468
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

Crack Growth Simulation Under Complicated Stress Field Using S-Version FEM

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Koichi Masaki, Kazuya Osakabe, Akiyuki Takahashi, Yoshitaka Wada, Masanori Kikuchi
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A010, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63698
https://doi.org/10.1115/PVP2016-63698
View Paper titled, Crack Growth Simulation Under Complicated Stress Field Using S-Version FEM
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Topics: Finite element methods, Finite element model, Fracture (Materials), Simulation, Stress, Finite element analysis, Thermal stresses, Welding
Proceedings Papers

Study on Application of PFM Analysis Method to Japanese Code for RPV Integrity Assessment Under PTS Events

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Kazuya Osakabe, Koichi Masaki, Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Shinobu Yoshimura
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A055, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45497
https://doi.org/10.1115/PVP2015-45497
View Paper titled, Study on Application of PFM Analysis Method to Japanese Code for RPV Integrity Assessment Under PTS Events
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Topics: Cracking (Materials), Fracture (Process), Fracture mechanics, Fracture toughness, Pressure, Reactor vessels, Uncertainty
Proceedings Papers

Estimation of Through-Wall Cracking Frequency of RPV Under PTS Events Using PFM Analysis Method for Identifying Conservatism Included in Current Japanese Code

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Kazuya Osakabe, Koichi Masaki, Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A096, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28621
https://doi.org/10.1115/PVP2014-28621
View Paper titled, Estimation of Through-Wall Cracking Frequency of RPV Under PTS Events Using PFM Analysis Method for Identifying Conservatism Included in Current Japanese Code
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Topics: Cracking (Materials), Fracture (Process), Fracture (Materials), Fracture mechanics, Fracture toughness, Pressure, Reactor vessels, Reliability, Stress, Thermal shock
Proceedings Papers

Structural Integrity Evaluation of Reactor Pressure Vessels During PTS Events Using Deterministic and Probabilistic Fracture Mechanics Analysis

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Kazuya Osakabe, Hiroyuki Nishikawa, Koichi Masaki, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A044, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97923
https://doi.org/10.1115/PVP2013-97923
View Paper titled, Structural Integrity Evaluation of Reactor Pressure Vessels During PTS Events Using Deterministic and Probabilistic Fracture Mechanics Analysis
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Topics: Fracture mechanics, Reactor vessels, Design for Manufacturing, Fracture (Materials), Accidents, Coolants, Fracture toughness, Probability, Reliability, Steam
Proceedings Papers

Study on Weld Residual Stress and Crack Propagation Evaluations for a Saddle-Shaped Weld Joint

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Jinya Katsuyama, Koichi Masaki, Kunio Onizawa
Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A081, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97838
https://doi.org/10.1115/PVP2013-97838
View Paper titled, Study on Weld Residual Stress and Crack Propagation Evaluations for a Saddle-Shaped Weld Joint
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Topics: Crack propagation, Stress, Pipes, Finite element methods, Corners (Structural elements), Failure, Finite element analysis, Fitness-for-service, Fracture (Materials), Heat
Journal Articles

Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events

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Koichi Masaki, Jinya Katsuyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2014, 136(1): 011208.
Paper No: PVT-13-1034
https://doi.org/10.1115/1.4025615
Published Online: November 27, 2013
View Articletitled, Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events
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Topics: Fracture (Materials), Probability, Reactor vessels, Thermal shock, Transients (Dynamics), Temperature, Sensitivity analysis, Fracture mechanics, Neutrons, Fluence (Radiation measurement)
Journal Articles

Effect of Partial Welding on the Residual Stress and Structural Integrity of Piping Welds

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Jinya Katsuyama, Koichi Masaki, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2013, 135(6): 061403.
Paper No: PVT-12-1149
https://doi.org/10.1115/1.4025087
Published Online: October 10, 2013
View Articletitled, Effect of Partial Welding on the Residual Stress and Structural Integrity of Piping Welds
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Topics: Maintenance, Stress, Welding, Pipes, Welded joints, Finite element methods, Stress concentration
Proceedings Papers

Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During PTS Events

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Kunio Onizawa, Koichi Masaki, Jinya Katsuyama
Proc. ASME. PVP2012, Volume 1: Codes and Standards, 695-701, July 15–19, 2012
Publisher: American Society of Mechanical Engineers
Paper No: PVP2012-78836
https://doi.org/10.1115/PVP2012-78836
View Paper titled, Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During PTS Events
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Topics: Reactor vessels, Fracture (Materials), Probability, Fracture mechanics, Sensitivity analysis, Temperature, Thermal shock
Proceedings Papers

Effect of Partial Welding on Residual Stress and Structural Integrity in Piping Welds

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Jinya Katsuyama, Koichi Masaki, Kunio Onizawa
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 1287-1295, July 15–19, 2012
Publisher: American Society of Mechanical Engineers
Paper No: PVP2012-78838
https://doi.org/10.1115/PVP2012-78838
View Paper titled, Effect of Partial Welding on Residual Stress and Structural Integrity in Piping Welds
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Topics: Pipes, Stress, Welded joints, Welding, Maintenance, Butt welding, Compressive stress, Cutting, Fracture mechanics, Inspection