1-17 of 17
Hisashi Takamizawa
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

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

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
Open the PDF for Development of Stress Intensity Factor Solution for Surface Crack at Nozzle Corner in Reactor Pressure Vessel in another window
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

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
Open the PDF for Analysis of the Effect of Pre-Crack Curvature in Mini-C(T) Specimen on Fracture Toughness Evaluation in another window
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

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
Open the PDF for Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel in another window
Topics: Base metals, Cladding systems (Building), Fracture toughness, Heat, Steel, Overlays (Materials engineering), Reactor vessels
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
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
Open the PDF for Assessment of Residual Stress for Thick Butt-Welded Plate of a Reactor Pressure Vessel Steel in another window
Topics: Drilling, Finite element analysis, Reactor vessels, Steel, Stress
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
Open the PDF for Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels in another window
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
Open the PDF for Fracture Toughness in Postulated Crack Area of PTS Evaluation in Highly-Neutron Irradiated RPV Steel in another window
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
Open the PDF for Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel in another window
Topics: Cladding systems (Building), Finite element analysis, Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Surface cracks
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
Publisher: ASME
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
Open the PDF for Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction in another window
Topics: Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Surveillance, Steel, Temperature, Uncertainty
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
Open the PDF for Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel in another window
Topics: Finite element analysis, Fracture (Materials), Fracture mechanics, Fracture toughness, Reactor vessels, Steel, Surface cracks, Cladding systems (Building), Stress, Anisotropy
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
Publisher: American Society of Mechanical Engineers
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
Open the PDF for Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels in another window
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
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
Open the PDF for Susceptibility to Neutron Irradiation Embrittlement of Heat-Affected Zone of Reactor Pressure Vessel Steels in another window
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
Open the PDF for Fracture Toughness Evaluation of Heat-Affected Zone Under Weld Overlay Cladding in Reactor Pressure Vessel Steel in another window
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
Open the PDF for Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels in another window
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
Open the PDF for Fracture Toughness Evaluation of Neutron-Irradiated Reactor Pressure Vessel Steel Using Miniature-C(T) Specimens in another window
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
Publisher: American Society of Mechanical Engineers
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
Open the PDF for Bayesian Statistical Analysis on Chemical Composition Contributing to Irradiation Embrittlement at High Fluence Region in another window
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
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
Open the PDF for Specimen Size Effect on Fracture Toughness of Reactor Pressure Vessel Steel Following Warm Pre-Stressing in another window
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
Open the PDF for Finite Element Analysis on the Application of Mini-C(T) Test Specimens for Fracture Toughness Evaluation in another window
Topics: Finite element analysis, Fracture toughness, Fatigue, Fracture (Materials), Metals, Plane strain, Steel, Stress, Surveillance, Temperature