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Jinya Katsuyama
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Journal Articles

Benchmark Analysis of Ductile Fracture Simulation for Circumferentially Cracked Pipes Subjected to Bending

Tomohisa Kumagai, Yasufumi Miura, Naoki Miura, Stephane Marie, Remmal Almahdi, Akihiro Mano, Yinsheng Li, Jinya Katsuyama, Yoshitaka Wada, Jin-ha Hwang, Yun-Jae Kim, Toshio Nagashima, Nam-Su Huh, Akiyuki Takahashi
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011509.
Paper No: PVT-21-1106
DOI: https://doi.org/10.1115/1.4052852
Published Online: December 6, 2021
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Topics: Fracture (Materials), Pipes, Stress, Fracture (Process), Finite element model
Proceedings Papers

Assessment of Residual Stress for Thick Butt-Welded Plate of a Reactor Pressure Vessel Steel

Yoosung Ha, Shigetaka Okano, Hisashi Takamizawa, Jinya Katsuyama, Masahito Mochizuki
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A067, July 13–15, 2021
Paper No: PVP2021-61897
DOI: https://doi.org/10.1115/PVP2021-61897
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Topics: Drilling, Finite element analysis, Reactor vessels, Steel, Stress
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

Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

Takatoshi Hirota, Yasuto Nagoshi, Kiminobu Hojo, Hiroshi Okada, Akiyuki Takahashi, Jinya Katsuyama, Takashi Ueda, Takuya Ogawa, Kenji Yashirodai, Mitsuru Ohata, Fumiyoshi Minami
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A056, July 13–15, 2021
Paper No: PVP2021-61668
DOI: https://doi.org/10.1115/PVP2021-61668
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Topics: Brittleness, Computer simulation, Damage, Deformation, Ductile fracture, Ductile-brittle transition, Evaluation methods, Finite element analysis, Finite element model, Flat plates
Proceedings Papers

Benchmarking Study on Probabilistic Fracture Mechanics Analysis Codes xLPR and PASCAL-SP Considering Primary Water Stress Corrosion Cracking

Akihiro Mano, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A027, July 13–15, 2021
Paper No: PVP2021-61202
DOI: https://doi.org/10.1115/PVP2021-61202
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Topics: Fracture mechanics, Stress corrosion cracking, Water
Proceedings Papers

Fracture Toughness in Postulated Crack Area of PTS Evaluation in Highly-Neutron Irradiated RPV Steel

Yoosung Ha, Masaki Shimodaira, Hisashi Takamizawa, Tohru Tobita, Jinya Katsuyama, Yutaka Nishiyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A058, July 13–15, 2021
Paper No: PVP2021-61892
DOI: https://doi.org/10.1115/PVP2021-61892
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Topics: Fracture (Materials), Fracture toughness, Heat, Neutrons, Steel, Vickers hardness testing
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
Journal Articles

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP Regarding Stress Corrosion Cracking in Nickel Based Alloy Weld Joint of Piping System in Boiling Water Reactor

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011506.
Paper No: PVT-21-1094
DOI: https://doi.org/10.1115/1.4052449
Published Online: October 8, 2021
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Topics: Alloys, Boiling water reactors, Failure, Fracture (Materials), Nickel, Probability, Sensitivity analysis, Piping systems, Stress corrosion cracking, Leakage
Journal Articles

Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel

Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011304.
Paper No: PVT-21-1049
DOI: https://doi.org/10.1115/1.4051704
Published Online: August 4, 2021
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Topics: Cladding systems (Building), Finite element analysis, Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Surface cracks
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
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A049, August 3, 2020
Paper No: PVP2020-21441
DOI: https://doi.org/10.1115/PVP2020-21441
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Topics: Finite element analysis, Fracture (Materials), Fracture mechanics, Fracture toughness, Reactor vessels, Steel, Surface cracks, Cladding systems (Building), Stress, Anisotropy
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

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

Akihiro Mano, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A063, August 3, 2020
Paper No: PVP2020-21427
DOI: https://doi.org/10.1115/PVP2020-21427
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Topics: Fracture mechanics, Stress corrosion cracking, Water, Stress, Boiling water reactors, Collaboration, Failure, Fatigue, Nuclear power, Nuclear power stations
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
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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

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
DOI: https://doi.org/10.1115/1.4045874
Published Online: February 24, 2020
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Topics: Failure, Fracture (Materials), Fracture toughness, Neutrons, Reactor vessels, Transients (Dynamics), Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure)
Journal Articles

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

Kai Lu, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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
Journal Articles

Crack Growth Evaluation for Cracked Stainless and Carbon Steel Pipes Under Large Seismic Cyclic Loading

Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021906.
Paper No: PVT-18-1082
DOI: https://doi.org/10.1115/1.4045133
Published Online: November 22, 2019
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Topics: Evaluation methods, Fracture (Materials), Pipes, Stress
Proceedings Papers

Susceptibility to Neutron Irradiation Embrittlement of Heat-Affected Zone of Reactor Pressure Vessel Steels

Hisashi Takamizawa, Jinya Katsuyama, Yoosung Ha, Tohru Tobita, Yutaka Nishiyama, Kunio Onizawa
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A022, July 14–19, 2019
Paper No: PVP2019-94011
DOI: https://doi.org/10.1115/PVP2019-94011
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Topics: Embrittlement, Heat, Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel