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Shigeaki Tanaka
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Proceedings Papers

Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material

Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Yasuhiro Hattori, Tetsushi Yamaoka, Shigeaki Tanaka, Toshiyuki Saito
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A047, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61467
https://doi.org/10.1115/PVP2021-61467
View Paper titled, Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material
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Topics: Alloy steel, Alloys, Boiling water reactors, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Reactor vessels, Stress corrosion cracking
Proceedings Papers

Investigation on the Effects of Carbon Macro-Segregation of Mechanical Properties Using a Large-Scale Forged Low Alloy Steel for a BWR Reactor Pressure Vessel

Takahiro Hayashi, Takuya Ogawa, Rie Sumiya, Tetsushi Yamaoka, Shigeaki Tanaka, Yasuhiro Hattori, Atsushi Mori
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A082, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21857
https://doi.org/10.1115/PVP2020-21857
View Paper titled, Investigation on the Effects of Carbon Macro-Segregation of Mechanical Properties Using a Large-Scale Forged Low Alloy Steel for a BWR Reactor Pressure Vessel
Open the PDF for Investigation on the Effects of Carbon Macro-Segregation of Mechanical Properties Using a Large-Scale Forged Low Alloy Steel for a BWR Reactor Pressure Vessel in another window
Topics: Alloy steel, Boiling water reactors, Carbon, Fracture toughness, Iron and steel making, Mechanical properties, Pressure vessels, Reactor vessels
Proceedings Papers

Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

Masato Koshiishi, Hitoshi Seto, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A073, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21332
https://doi.org/10.1115/PVP2020-21332
View Paper titled, Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition
Open the PDF for Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition in another window
Topics: Boiling water reactors, Irradiation (Radiation exposure), Neutrons, Stainless steel, Stress corrosion cracking, Fracture (Materials), Grain boundaries, Mechanical properties
Proceedings Papers

Evaluation of Crack Growth Rate of Neutron Irradiated Austenitic Stainless Steels at High Stress Intensity Factor Levels

Hitoshi Seto, Masato Koshiishi, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A075, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21365
https://doi.org/10.1115/PVP2020-21365
View Paper titled, Evaluation of Crack Growth Rate of Neutron Irradiated Austenitic Stainless Steels at High Stress Intensity Factor Levels
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Topics: Fracture (Materials), Neutrons, Stainless steel, Stress
Proceedings Papers

Fracture Toughness Criteria of Irradiated Austenitic Stainless Steels for Structural Integrity Evaluation of BWR Internal Components

Takahiro Hayashi, Shigeaki Tanaka, Tomonori Abe, Seiji Sakuraya, Suguru Ooki, Takayuki Kaminaga
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A017, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93441
https://doi.org/10.1115/PVP2019-93441
View Paper titled, Fracture Toughness Criteria of Irradiated Austenitic Stainless Steels for Structural Integrity Evaluation of BWR Internal Components
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Topics: Boiling water reactors, Fracture toughness, Irradiation (Radiation exposure), Neutrons, Stainless steel
Proceedings Papers

IASCC Evaluation Method for Irradiated Core Internal Structures in BWR Power Plants

Kenichi Takakura, Shigeaki Tanaka, Tomomi Nakamura, Kazuhiro Chatani, Yoshiyuki Kaji
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 675-684, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25293
https://doi.org/10.1115/PVP2010-25293
View Paper titled, IASCC Evaluation Method for Irradiated Core Internal Structures in BWR Power Plants
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Topics: Boiling water reactors, Evaluation methods, Power stations, Fluence (Radiation measurement), Stress, Fracture (Materials), Irradiation (Radiation exposure), Neutrons, Safety, Water
Proceedings Papers

Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width

Tadahiko Torimaru, Masanari Sugiyama, Hiroshi Sakamoto, Shigeaki Tanaka, Tomomi Nakamura
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 375-385, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75233
https://doi.org/10.1115/ICONE17-75233
View Paper titled, Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width
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Topics: Fracture toughness, Stainless steel, Dimensions, Boiling water reactors, ASTM International, Fatigue cracks, Fluence (Radiation measurement), Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure)