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Yutaka Nishiyama
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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
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
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

Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction

Hisashi Takamizawa, Yutaka Nishiyama
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. October 2021, 143(5): 051502.
Paper No: PVT-20-1142
https://doi.org/10.1115/1.4050317
Published Online: March 22, 2021
View Article titled, Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction
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Topics: Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Surveillance, Steel, Temperature, Uncertainty
Proceedings Papers

Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels

Hisashi Takamizawa, Yutaka Nishiyama, Takashi Hirano
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A065, August 3, 2020
Paper No: PVP2020-21698
https://doi.org/10.1115/PVP2020-21698
View Paper titled, Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels
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Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Notch testing, Phase transition temperature, Reactor vessels, Statistics, Steel, Uncertainty
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
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
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
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
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

Bayesian Statistical Analysis on Chemical Composition Contributing to Irradiation Embrittlement at High Fluence Region

Hisashi Takamizawa, Yutaka Nishiyama
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A040, July 17–21, 2016
Paper No: PVP2016-63822
https://doi.org/10.1115/PVP2016-63822
View Paper titled, Bayesian Statistical Analysis on Chemical Composition Contributing to Irradiation Embrittlement at High Fluence Region
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Topics: Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Statistical analysis, Damage, Neutrons, Pressurized water reactors, Reactor vessels, Statistical distributions, Surveillance
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
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
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
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

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
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

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
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
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
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
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
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

Numerical Simulation of Irradiation-Induced Grain-Boundary Phosphorous Segregation in Reactor Pressure Vessel Steels Using Rate Theory Model With First-Principles Calculations

Ken-ichi Ebihara, Masatake Yamaguchi, Yutaka Nishiyama, Kunio Onizawa, Hiroshi Matsuzawa
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 395-402, July 26–30, 2009
Paper No: PVP2009-77624
https://doi.org/10.1115/PVP2009-77624
View Paper titled, Numerical Simulation of Irradiation-Induced Grain-Boundary Phosphorous Segregation in Reactor Pressure Vessel Steels Using Rate Theory Model With First-Principles Calculations
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Topics: Computer simulation, Grain boundaries, Irradiation (Radiation exposure), Reactor vessels, Steel, Temperature, Neutrons, Simulation, Databases, Fracture (Materials)