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Jinya Katsuyama
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Proceedings Papers

Biaxial Constraint Effect on Fracture Toughness Evaluation of Reactor Pressure Vessel Under Pressurized Thermal Shock Events

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Masaki Shimodaira, Yoshihito Yamaguchi, Keiko Iwata, Jinya Katsuyama, Yasuhiro Chimi
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A065, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123136
https://doi.org/10.1115/PVP2024-123136
View Paper titled, Biaxial Constraint Effect on Fracture Toughness Evaluation of Reactor Pressure Vessel Under Pressurized Thermal Shock Events
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Topics: Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Thermal shock
Proceedings Papers

Effects of Welding and Constraint Conditions on the Welding Residual Stress and Hardness of Type 316 Stainless Steel Pipe

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Suo Li, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A023, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122731
https://doi.org/10.1115/PVP2024-122731
View Paper titled, Effects of Welding and Constraint Conditions on the Welding Residual Stress and Hardness of Type 316 Stainless Steel Pipe
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Topics: Finite element analysis, Pipes, Stainless steel, Stress, Stress corrosion cracking, Welding
Proceedings Papers

Modeling of Hardness and Welding Residual Stress in Type 316 Stainless Steel Components for the Assessment of Stress Corrosion Cracking

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Suo Li, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li, Dean Deng
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A094, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-103449
https://doi.org/10.1115/PVP2023-103449
View Paper titled, Modeling of Hardness and Welding Residual Stress in Type 316 Stainless Steel Components for the Assessment of Stress Corrosion Cracking
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Topics: Finite element analysis, Modeling, Stainless steel, Stress, Stress corrosion cracking, Welding
Proceedings Papers

Development of Stress Intensity Factor Solution for Surface Crack at Nozzle Corner in Reactor Pressure Vessel

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Yoshihito Yamaguchi, Hisashi Takamizawa, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A025, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106210
https://doi.org/10.1115/PVP2023-106210
View Paper titled, Development of Stress Intensity Factor Solution for Surface Crack at Nozzle Corner in Reactor Pressure Vessel
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Topics: Corners (Structural elements), Nozzles, Reactor vessels, Stress, Surface cracks
Proceedings Papers

Analysis of the Effect of Pre-Crack Curvature in Mini-C(T) Specimen on Fracture Toughness Evaluation

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Masaki Shimodaira, Yoosung Ha, Hisashi Takamizawa, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A027, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-102699
https://doi.org/10.1115/PVP2023-102699
View Paper titled, Analysis of the Effect of Pre-Crack Curvature in Mini-C(T) Specimen on Fracture Toughness Evaluation
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Topics: Finite element analysis, Fracture (Materials), Fracture toughness
Journal Articles

Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel

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Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021501.
Paper No: PVT-22-1083
https://doi.org/10.1115/1.4055626
Published Online: December 2, 2022
View Articletitled, Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel
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Topics: Base metals, Cladding systems (Building), Fracture toughness, Heat, Steel, Overlays (Materials engineering), Reactor vessels
Proceedings Papers

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

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Jinya Katsuyama, Yoshihito Yamaguchi, Yoshiyuki Nemoto, Takuya Furuta, Yoshiyuki Kaji
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A030, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84609
https://doi.org/10.1115/PVP2022-84609
View Paper titled, Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations
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Topics: Accidents, Boiling water reactors, Creep, Damage, Physics, Radiation (Physics), Simulation, Thermal hydraulics
Proceedings Papers

State-of-the-Art of WPS in RPV PTS Analysis

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Maksym Zarazovskii, Vladislav Pištora, Dana Lauerova, Florian Obermeier, Diego Fernando Mora Mendez, Yaroslav Dubyk, Tobias Bolinder, Carlos Cueto-Felgueroso Garcia, Szabolcs Szávai, Judit Dudra, Oriol Costa Garrido, Christophe Blain, Markku Puustinen, Jinya Katsuyama, B. Richard Bass, Paul T. Williams, Oleksii Shugailo
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A083, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83699
https://doi.org/10.1115/PVP2022-83699
View Paper titled, State-of-the-Art of WPS in RPV PTS Analysis
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Topics: Brittle fracture, Ductile fracture, Fracture (Materials), Fracture toughness, Heat, Reactor vessels, Steel, Stress, Thermal shock, Transients (Dynamics)
Journal Articles

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

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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
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011509.
Paper No: PVT-21-1106
https://doi.org/10.1115/1.4052852
Published Online: December 6, 2021
View Articletitled, Benchmark Analysis of Ductile Fracture Simulation for Circumferentially Cracked Pipes Subjected to Bending
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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

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Yoosung Ha, Shigetaka Okano, Hisashi Takamizawa, Jinya Katsuyama, Masahito Mochizuki
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A067, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61897
https://doi.org/10.1115/PVP2021-61897
View Paper titled, Assessment of Residual Stress for Thick Butt-Welded Plate of a Reactor Pressure Vessel Steel
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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

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Masaki Shimodaira, Tohru Tobita, Yasuto Nagoshi, Kai Lu, Jinya Katsuyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A057, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61725
https://doi.org/10.1115/PVP2021-61725
View Paper titled, Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61668
https://doi.org/10.1115/PVP2021-61668
View Paper titled, Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee
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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

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Akihiro Mano, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A027, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61202
https://doi.org/10.1115/PVP2021-61202
View Paper titled, Benchmarking Study on Probabilistic Fracture Mechanics Analysis Codes xLPR and PASCAL-SP Considering Primary Water Stress Corrosion Cracking
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61892
https://doi.org/10.1115/PVP2021-61892
View Paper titled, Fracture Toughness in Postulated Crack Area of PTS Evaluation in Highly-Neutron Irradiated RPV Steel
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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

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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

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

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Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011506.
Paper No: PVT-21-1094
https://doi.org/10.1115/1.4052449
Published Online: October 8, 2021
View Articletitled, 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
Open the PDF for 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 in another window
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

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Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011304.
Paper No: PVT-21-1049
https://doi.org/10.1115/1.4051704
Published Online: August 4, 2021
View Articletitled, Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel
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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

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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

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

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Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A049, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21441
https://doi.org/10.1115/PVP2020-21441
View Paper titled, Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel
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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

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Kai Lu, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A062, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21421
https://doi.org/10.1115/PVP2020-21421
View Paper titled, Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor
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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)