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Proceedings Papers

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

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

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
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021906.
Paper No: PVT-18-1082
https://doi.org/10.1115/1.4045133
Published Online: November 22, 2019
View Article titled, Crack Growth Evaluation for Cracked Stainless and Carbon Steel Pipes Under Large Seismic Cyclic Loading
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-94011
https://doi.org/10.1115/PVP2019-94011
View Paper titled, Susceptibility to Neutron Irradiation Embrittlement of Heat-Affected Zone of Reactor Pressure Vessel Steels
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Topics: Embrittlement, Heat, Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel
Proceedings Papers

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

Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li, Kunio Onizawa
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A066, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45834
https://doi.org/10.1115/PVP2015-45834
View Paper titled, Crack Growth Evaluation for Cracked Carbon and Stainless Steel Pipes Under Large Seismic Cyclic Loading
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Topics: Carbon, Fracture (Materials), Pipes, Stainless steel, Earthquakes, Evaluation methods, Carbon steel, Design, Nuclear power stations, Waves
Proceedings Papers

Finite Element Analysis on the Application of Mini-C(T) Test Specimens for Fracture Toughness Evaluation

Hisashi Takamizawa, Tohru Tobita, Takuyo Ohtsu, Jinya Katsuyama, Yutaka Nishiyama, Kunio Onizawa
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A060, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45412
https://doi.org/10.1115/PVP2015-45412
View Paper titled, Finite Element Analysis on the Application of Mini-C(T) Test Specimens for Fracture Toughness Evaluation
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Topics: Finite element analysis, Fracture toughness, Fatigue, Fracture (Materials), Metals, Plane strain, Steel, Stress, Surveillance, Temperature
Proceedings Papers

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

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

Development of Probabilistic Evaluation Models of Fracture Toughness K Ic and K Ia for Japanese RPV Steels

Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Kazuya Osakabe, Kentaro Yoshimoto
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A017, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45915
https://doi.org/10.1115/PVP2015-45915
View Paper titled, Development of Probabilistic Evaluation Models of Fracture Toughness K Ic and K Ia for Japanese RPV Steels
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Topics: Fracture toughness, Steel, Databases, Electromagnetic scattering, Fracture (Materials), Fracture (Process), Fracture mechanics, Log normal distribution, Probability, Reactor vessels
Proceedings Papers

Effects of Plasticity on the Stress Intensity Factor Evaluation for Underclad Crack Under Pressurized Thermal Shock Events

Jinya Katsuyama, Ling Huang, Yinsheng Li, Kunio Onizawa
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A054, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45411
https://doi.org/10.1115/PVP2015-45411
View Paper titled, Effects of Plasticity on the Stress Intensity Factor Evaluation for Underclad Crack Under Pressurized Thermal Shock Events
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Topics: Fracture (Materials), Plasticity, Stress, Thermal shock, Cladding systems (Building), Evaluation methods, Corrosion protection, Crack propagation, Finite element methods, Geometry
Proceedings Papers

Development of J-Integral Solutions for Semi-Elliptical Circumferential Cracked Pipes Subjected to Internal Pressure and Bending Moment

Makoto Udagawa, Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li, Kunio Onizawa
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A023, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45763
https://doi.org/10.1115/PVP2015-45763
View Paper titled, Development of J-Integral Solutions for Semi-Elliptical Circumferential Cracked Pipes Subjected to Internal Pressure and Bending Moment
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Topics: Pipes, Pressure, Finite element analysis, Fracture (Materials), Surface cracks, Piping systems, Dimensions, Failure, Fracture mechanics, Materials properties
Journal Articles

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens

Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2015, 137(5): 051405.
Paper No: PVT-14-1156
https://doi.org/10.1115/1.4029428
Published Online: October 1, 2015
View Article titled, Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
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Topics: Fracture toughness, Steel, Temperature, Tension, Reactor vessels
Proceedings Papers

Benchmark Analysis on Probabilistic Fracture Mechanics Analysis Codes Considering Multiple Cracks and Crack Initiation in Aged Piping of Nuclear Power Plants

Yinsheng Li, Kazuya Osakabe, Genshichiro Katsumata, Jinya Katsuyama, Kunio Onizawa, Shinobu Yoshimura
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A058, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28513
https://doi.org/10.1115/PVP2014-28513
View Paper titled, Benchmark Analysis on Probabilistic Fracture Mechanics Analysis Codes Considering Multiple Cracks and Crack Initiation in Aged Piping of Nuclear Power Plants
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Topics: Fracture (Materials), Fracture mechanics, Nuclear power stations, Pipes, Risk assessment, Probability, Crack detection, Failure, In-service inspection, Piping systems
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

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

Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Tadashi Watanabe, Yutaka Nishiyama
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A097, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28645
https://doi.org/10.1115/PVP2014-28645
View Paper titled, Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
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Topics: Reactor vessels, Structural analysis, Thermal hydraulics, Coolants, Water, Crack propagation, Fracture (Materials), Heat transfer coefficients, Pressure vessels, Pressurized water reactors
Proceedings Papers

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions

Masato Yamamoto, Akihiko Kimura, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Yasuhiro Mabuchi, Hans-Werner Viehrig, Naoki Miura, Naoki Soneda
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A098, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28898
https://doi.org/10.1115/PVP2014-28898
View Paper titled, A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions
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Topics: Temperature, Fracture toughness, Testing, Electromagnetic scattering, Machinery, Steel, Surveillance, ASTM International, Dimensions, Reliability
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

Yoshihito Yamaguchi, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa, Yutaka Nishiyama, Yinsheng Li
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30643
https://doi.org/10.1115/ICONE22-30643
View Paper titled, Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes
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Topics: Earthquakes, Fracture mechanics, Pipes, Failure, Fracture (Materials), Probability, Sensitivity analysis, Evaluation methods
Proceedings Papers

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens

Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A043, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97897
https://doi.org/10.1115/PVP2013-97897
View Paper titled, Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens
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Topics: Fracture toughness, Reactor vessels, Steel, ASTM International, Brittleness, Phase transition temperature, Shapes, Temperature
Proceedings Papers

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

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

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens — 2nd Report: Fracture Toughness Comparison in Specified Loading Rate Condition

Masato Yamamoto, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Yasuhiro Mabuchi, Naoki Miura
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A045, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97936
https://doi.org/10.1115/PVP2013-97936
View Paper titled, A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens — 2nd Report: Fracture Toughness Comparison in Specified Loading Rate Condition
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Topics: Fracture toughness, Deformation, Electromagnetic scattering, Steel, Surveillance, Dimensions, Governments, Reliability, Temperature
Proceedings Papers

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

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
Proceedings Papers

Alternative Reference Temperature Based on Master Curve Approach in Japanese Reactor Pressure Vessel Steel

Takatoshi Hirota, Takashi Hirano, Kunio Onizawa
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A048, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-98164
https://doi.org/10.1115/PVP2013-98164
View Paper titled, Alternative Reference Temperature Based on Master Curve Approach in Japanese Reactor Pressure Vessel Steel
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Topics: Reactor vessels, Steel, Temperature, Fracture toughness, ASTM International, Base metals, Metals, Nuclear power stations, Safety