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Journal Articles

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

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 Article titled, 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

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
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

Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels

Keiko Iwata, Kuniki Hata, Tohru Tobita, Takatoshi Hirota, Hisashi Takamizawa, Yasuhiro Chimi, Yutaka Nishiyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A059, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61893
https://doi.org/10.1115/PVP2021-61893
View Paper titled, Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels
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Topics: Brittleness, Fracture (Materials), Fracture toughness, Notch testing, Reactor vessels, Steel
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
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
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
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 Article titled, 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
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
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

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

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

Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Satoshi Hanawa, Yutaka Nishiyama
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A067, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84535
https://doi.org/10.1115/PVP2018-84535
View Paper titled, Fracture Toughness Evaluation of Heat-Affected Zone Under Weld Overlay Cladding in Reactor Pressure Vessel Steel
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Topics: Cladding systems (Building), Fracture toughness, Heat, Overlays (Materials engineering), Reactor vessels, Steel, Strips, Base metals, Pressure vessels, Temperature
Journal Articles

Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels

Yoosung Ha, Tohru Tobita, Takuyo Ohtsu, Hisashi Takamizawa, Yutaka Nishiyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2018, 140(5): 051402.
Paper No: PVT-18-1039
https://doi.org/10.1115/1.4040642
Published Online: August 2, 2018
View Article titled, Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
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Topics: Fracture toughness, Neutrons, Steel, Temperature, Reactor vessels, Tension, Electromagnetic scattering
Proceedings Papers

Fracture Toughness Evaluation of Neutron-Irradiated Reactor Pressure Vessel Steel Using Miniature-C(T) Specimens

Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Yutaka Nishiyama
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A067, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65568
https://doi.org/10.1115/PVP2017-65568
View Paper titled, Fracture Toughness Evaluation of Neutron-Irradiated Reactor Pressure Vessel Steel Using Miniature-C(T) Specimens
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Topics: Fracture toughness, Neutrons, Reactor vessels, Steel, Temperature, Electromagnetic scattering, Phase transition temperature
Proceedings Papers

Specimen Size Effect on Fracture Toughness of Reactor Pressure Vessel Steel Following Warm Pre-Stressing

Keiko Iwata, Tohru Tobita, Hisashi Takamizawa, Yasuhiro Chimi, Kentaro Yoshimoto, Yutaka Nishiyama
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A017, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63795
https://doi.org/10.1115/PVP2016-63795
View Paper titled, Specimen Size Effect on Fracture Toughness of Reactor Pressure Vessel Steel Following Warm Pre-Stressing
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Topics: Fracture toughness, Reactor vessels, Size effect, Steel, Stress, Engineering models, Fracture (Materials), Fracture (Process), Thermomechanics, Transients (Dynamics)
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
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

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
Journal Articles

Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel

Jinya Katsuyama, Tohru Tobita, Yutaka Nishiyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Materials And Fabrication
J. Pressure Vessel Technol. June 2012, 134(3): 031402.
https://doi.org/10.1115/1.4005868
Published Online: May 18, 2012
View Article titled, Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
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Topics: Base metals, Fracture toughness, Grain size, Heat, Heat treating (Metalworking), Mechanical properties, Reactor vessels, Steel, Surveillance, Temperature
Journal Articles

Effect of Welding Conditions on Residual Stress and Stress Corrosion Cracking Behavior at Butt-Welding Joints of Stainless Steel Pipes

Jinya Katsuyama, Tohru Tobita, Hiroto Itoh, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2012, 134(2): 021403.
https://doi.org/10.1115/1.4005391
Published Online: January 11, 2012
View Article titled, Effect of Welding Conditions on Residual Stress and Stress Corrosion Cracking Behavior at Butt-Welding Joints of Stainless Steel Pipes
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Topics: Butt welding, Heat, Pipes, Stress, Stress concentration, Welding, Stainless steel, Stress corrosion cracking, Finite element analysis
Proceedings Papers

Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel

Jinya Katsuyama, Tohru Tobita, Yutaka Nishiyama, Kunio Onizawa
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 585-592, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25561
https://doi.org/10.1115/PVP2010-25561
View Paper titled, Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
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Topics: Heat, Reactor vessels, Base metals, Fracture toughness, Grain size, Irradiation (Radiation exposure), Mechanical properties, Steel, Embrittlement, Surveillance
Proceedings Papers

Effect of Welding Conditions on Residual Stress and SCC Behavior at Butt-Welding Joints of Recirculation Pipes

Jinya Katsuyama, Tohru Tobita, Hiroto Itoh, Kunio Onizawa
Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 441-449, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61430
https://doi.org/10.1115/PVP2008-61430
View Paper titled, Effect of Welding Conditions on Residual Stress and SCC Behavior at Butt-Welding Joints of Recirculation Pipes
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Topics: Butt welding, Pipes, Stress, Welding, Electromagnetic scattering, Fracture (Materials), Heat, Carbon, Countermeasures, Engineering simulation