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Journal Articles

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

Jinya Katsuyama, Kazuya Osakabe, Shumpei Uno, Yinsheng Li, Shinobu Yoshimura
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021205.
Paper No: PVT-19-1082
https://doi.org/10.1115/1.4045874
Published Online: February 24, 2020
View Article titled, Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels
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Topics: Failure, Fracture (Materials), Fracture toughness, Neutrons, Reactor vessels, Transients (Dynamics), Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure)
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
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

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
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 of Probabilistic Fracture Mechanics Analysis Code PASCAL Through Benchmark Analyses With FAVOR

Yinsheng Li, Shumpei Uno, Jinya Katsuyama, Terry Dickson, Mark Kirk
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A007, July 16–20, 2017
Paper No: PVP2017-66004
https://doi.org/10.1115/PVP2017-66004
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL Through Benchmark Analyses With FAVOR
Open the PDF for Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL Through Benchmark Analyses With FAVOR in another window
Topics: Fracture mechanics, Failure, Engineering standards, Nuclear power, Probability, Reactor vessels, Thermal shock
Proceedings Papers

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

Jinya Katsuyama, Kazuya Osakabe, Shumpei Uno, Yinsheng Li, Shinobu Yoshimura
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A004, July 16–20, 2017
Paper No: PVP2017-65921
https://doi.org/10.1115/PVP2017-65921
View Paper titled, Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels
Open the PDF for Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels in another window
Topics: Fracture mechanics, Reactor vessels, Embrittlement, Irradiation (Radiation exposure), Neutrons, Failure, Fracture (Process), Databases, Engineers, Nuclear power
Proceedings Papers

Verification Methodology and Results of Probabilistic Fracture Mechanics Code PASCAL

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
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

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
https://doi.org/10.1115/PVP2017-66003
View Paper titled, Probabilistic Fracture Mechanics Analysis Models for Japanese Reactor Pressure Vessels
Open the PDF for Probabilistic Fracture Mechanics Analysis Models for Japanese Reactor Pressure Vessels in another window
Topics: Fracture mechanics, Reactor vessels, Failure, Evaluation methods, Fracture (Materials), Nuclear power, Probability, Stress concentration, Welding
Proceedings Papers

Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

Shumpei Uno, Jinya Katsuyama, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A039, July 17–21, 2016
Paper No: PVP2016-63443
https://doi.org/10.1115/PVP2016-63443
View Paper titled, Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
Open the PDF for Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses in another window
Topics: Structural analysis, Thermal hydraulics, Coolants, Water, Heat transfer coefficients, Cladding systems (Building), Heat treating (Metalworking), Overlays (Materials engineering), Pressurized water reactors, Reactor vessels