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Proceedings Papers

Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region (Report 2)

Kiminobu Hojo, Takatoshi Hirota, Yasuto Nagoshi, Takuya Fukahori, Kimihisa Sakima, Mitsuru Ohata, Fumiyoshi Minami

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A003, July 17–22, 2022

Paper No: PVP2022-84186

DOI: https://doi.org/10.1115/PVP2022-84186

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Topics: Ductile-brittle transition, Fracture (Materials), Fracture (Process), Stress, Temperature

Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Satoshi Kumagai, Kiminobu Hojo, Takatoshi Hirota, Keiji Kawanishi

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A036, July 17–22, 2022

Paper No: PVP2022-84554

DOI: https://doi.org/10.1115/PVP2022-84554

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Topics: Ductile fracture, Finite element analysis, Pipes, Fracture (Materials), Coolants, Damage mechanics, Errors, Fracture mechanics, Nuclear reactors, Pressure

Proceedings Papers

Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region

Kiminobu Hojo, Takatoshi Hirota, Yasuto Nagoshi, Takuya Fukahori, Kimihisa Sakima, Mitsuru Ohata, Fumiyoshi Minami

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A055, July 13–15, 2021

Paper No: PVP2021-61318

DOI: https://doi.org/10.1115/PVP2021-61318

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Topics: Ductile fracture, Ductile-brittle transition, Fracture (Materials), Temperature

Proceedings Papers

Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

Takatoshi Hirota, Yasuto Nagoshi, Kiminobu Hojo, Hiroshi Okada, Akiyuki Takahashi, Jinya Katsuyama, Takashi Ueda, Takuya Ogawa, Kenji Yashirodai, Mitsuru Ohata, Fumiyoshi Minami

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A056, July 13–15, 2021

Paper No: PVP2021-61668

DOI: https://doi.org/10.1115/PVP2021-61668

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Topics: Brittleness, Computer simulation, Damage, Deformation, Ductile fracture, Ductile-brittle transition, Evaluation methods, Finite element analysis, Finite element model, Flat plates

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

DOI: https://doi.org/10.1115/PVP2021-61893

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Topics: Brittleness, Fracture (Materials), Fracture toughness, Notch testing, Reactor vessels, Steel

Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Satoshi Kumagai

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A047, August 3, 2020

Paper No: PVP2020-21645

DOI: https://doi.org/10.1115/PVP2020-21645

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Topics: Pipes, Fracture (Materials), Fracture (Process), Coolants, Ductile fracture, Fracture mechanics, Nuclear reactors, Pressure, Simulation, Stress

Proceedings Papers

Investigation of Temperature Dependence of Weibull Parameters of the Beremin Model in Ductile-Brittle Transition Temperature Region

Kiminobu Hojo, Naoki Ogawa, Kentaro Yoshimoto, Takatoshi Hirota, Yasuto Nagoshi

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A014, August 3, 2020

Paper No: PVP2020-21651

DOI: https://doi.org/10.1115/PVP2020-21651

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Topics: Ductile-brittle transition, Temperature, Temperature effects, Alloy steel, Fracture (Materials), Fracture (Process), Brittle fracture, Carbon steel, Ductile fracture, Electromagnetic scattering

Proceedings Papers

Improvement of Target Flaw Sizes of CASS Pipe for PD Approval Using PFM Code Preface

Wataru Nishi, Takatoshi Hirota, Mayumi Ochi, Daiki Takagoshi, Kiminobu Hojo

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A055, July 15–20, 2018

Paper No: PVP2018-85015

DOI: https://doi.org/10.1115/PVP2018-85015

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Topics: Pipes, Ferrites (Magnetic materials), Collapse, Mechanical properties, Stress, Ductile fracture, Failure mechanisms, Fracture mechanics, Nondestructive evaluation, Sensitivity analysis

Proceedings Papers

Fracture Analysis of Ductile-Brittle Transition Temperature Region Considering Specimens With Different Constraints

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Kentaro Yoshimoto, Yasuto Nagoshi, Shinichi Kawabata

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A057, July 15–20, 2018

Paper No: PVP2018-84385

DOI: https://doi.org/10.1115/PVP2018-84385

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Topics: Ductile-brittle transition, Fracture (Materials), Fracture (Process), Temperature, Electromagnetic scattering, Flat plates, Brittleness, Damage mechanics, Ductile fracture, Evaluation methods

Proceedings Papers

Study on Applicability of Master Curve Methodology Using Miniature C(T) Specimen to a Reactor Pressure Vessel With Low Upper Shelf Energy

Kentaro Yoshimoto, Takatoshi Hirota, Hiroyuki Sakamoto, Masato Oshikiri, Kazuya Tsutsumi, Takeshi Murakami

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A075, July 15–20, 2018

Paper No: PVP2018-84994

DOI: https://doi.org/10.1115/PVP2018-84994

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Topics: Reactor vessels, Fracture toughness, Irradiation (Radiation exposure), Neutrons, Steel, Countermeasures, Ductile fracture, Embrittlement, Fracture (Materials), Fracture (Process)

Proceedings Papers

Applicability of Miniature C(T) Specimen to Fracture Toughness Evaluation for the Irradiated Japanese Reactor Pressure Vessel Steel

Takuji Sugihara, Takatoshi Hirota, Hiroyuki Sakamoto, Kentaro Yoshimoto, Kazuya Tsutsumi, Takeshi Murakami

Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A073, July 16–20, 2017

Paper No: PVP2017-66206

DOI: https://doi.org/10.1115/PVP2017-66206

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Topics: Fracture toughness, Reactor vessels, Steel, Pressurized water reactors, Surveillance, Base metals, Metals, Electricity (Physics), Fatigue, Gas discharge (Electric discharge)

Proceedings Papers

Comparison of Prediction Models for Mechanical Properties of Thermally Aged Cast Austenitic Stainless Steels

Takatoshi Hirota, Mayumi Ochi, Kiminobu Hojo, Wataru Nishi, Shotaro Hayashi

Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A054, July 16–20, 2017

Paper No: PVP2017-65612

DOI: https://doi.org/10.1115/PVP2017-65612

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Topics: Mechanical properties, Stainless steel, Pressurized water reactors, Pipes, Databases, Ductile fracture, Ferrites (Magnetic materials), Fracture (Materials), Fracture (Process), Fracture toughness

Proceedings Papers

Study on Evaluation Procedure for Calculating the Stress Intensity Factor of Flaws Beneath RPV Cladding During Pressurised Thermal Shock Events by FE Analysis

Hiroyuki Sakamoto, Takatoshi Hirota, Naoki Ogawa

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A038, July 17–21, 2016

Paper No: PVP2016-63210

DOI: https://doi.org/10.1115/PVP2016-63210

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Topics: Cladding systems (Building), Finite element analysis, Stress, Thermal shock, Welding, Alloys, Steel, Cooling, Fracture (Materials), Reactor vessels

Proceedings Papers

Applicability of Fracture Toughness Curves Developed for Japanese Pressure Vessel Steels to Structural Integrity Evaluation

Kentaro Yoshimoto, Takatoshi Hirota, Hiroyuki Sakamoto

Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A053, July 19–23, 2015

Paper No: PVP2015-45275

DOI: https://doi.org/10.1115/PVP2015-45275

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Topics: Fracture toughness, Pressure vessels, Steel, Pressurized water reactors, Surveillance, Embrittlement, Indexing (Machining), Irradiation (Radiation exposure), Phase transition temperature, Reactor vessels

Proceedings Papers

Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels Against Pressurized Thermal Shock Events in Japan

Takatoshi Hirota, Hiroyuki Sakamoto, Naoki Ogawa

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A093, July 20–24, 2014

Paper No: PVP2014-28392

DOI: https://doi.org/10.1115/PVP2014-28392

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Topics: Reactor vessels, Thermal shock, Fracture toughness, Fracture mechanics, In-service inspection, Nuclear power stations, Pressurized water reactors

Proceedings Papers

Applicability of Miniature C(T) Specimen to Evaluation of Fracture Toughness for Reactor Pressure Vessel Steel

Kentaro Yoshimoto, Takatoshi Hirota, Hiroyuki Sakamoto, Takuji Sugihara, Shohei Sakaguchi, Toru Oumaya

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A056, July 14–18, 2013

Paper No: PVP2013-97840

DOI: https://doi.org/10.1115/PVP2013-97840

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Topics: Fracture toughness, Reactor vessels, Steel, Reliability, Surveillance, Dimensions, Electromagnetic scattering, Embrittlement, Evaluation methods, Irradiation (Radiation exposure)

Proceedings Papers

Evaluation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock

Naoki Ogawa, Kentaro Yoshimoto, Takatoshi Hirota, Shohei Sakaguchi, Toru Oumaya

Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A056, July 14–18, 2013

Paper No: PVP2013-97566

DOI: https://doi.org/10.1115/PVP2013-97566

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Topics: Reactor vessels, Thermal shock, Fracture (Materials), Fracture toughness, Accidents, Stress, Surface cracks, Coolants, Deformation, Finite element analysis

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

Paper No: PVP2013-98164

DOI: https://doi.org/10.1115/PVP2013-98164

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Topics: Reactor vessels, Steel, Temperature, Fracture toughness, ASTM International, Base metals, Metals, Nuclear power stations, Safety

Proceedings Papers

Development of Prediction Equations on Charpy Upper Shelf Energy for Japanese RPV Steels

Kazunobu Sakamoto, Takatoshi Hirota, Toru Osaki, Minoru Tomimatsu

Proc. ASME. PVP2003, Aging Management and Component Analysis, 9-16, July 20–24, 2003

Paper No: PVP2003-2149

DOI: https://doi.org/10.1115/PVP2003-2149

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Topics: Steel, Neutrons, Ductile-brittle transition, Economics , Embrittlement, Irradiation (Radiation exposure), Reactor vessels, Regression analysis, Surveillance, Temperature

Proceedings Papers

Simplified J-Integral Evaluation Method for Evaluation of Reactor Pressure Vessel in the Upper-Shelf Region

Yoshio Urabe, Seiji Asada, Takatoshi Hirota, Morihito Nakano, Ryuuichi Maeda

Proc. ASME. PVP2003, Design and Analysis Methods and Fitness for Service Evaluations for Pressure Vessels and Components, 31-39, July 20–24, 2003

Paper No: PVP2003-1925

DOI: https://doi.org/10.1115/PVP2003-1925

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Topics: Evaluation methods, Reactor vessels, Finite element analysis, Transients (Dynamics), Design, Elastic analysis, Computational methods, Cooling, Irradiation (Radiation exposure), Neutrons

Journal citation

NARROW

Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region (Report 2)

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Constraint Effect on Fracture in Ductile-Brittle Transition Temperature Region

Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

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

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Investigation of Temperature Dependence of Weibull Parameters of the Beremin Model in Ductile-Brittle Transition Temperature Region

Improvement of Target Flaw Sizes of CASS Pipe for PD Approval Using PFM Code Preface

Fracture Analysis of Ductile-Brittle Transition Temperature Region Considering Specimens With Different Constraints

Study on Applicability of Master Curve Methodology Using Miniature C(T) Specimen to a Reactor Pressure Vessel With Low Upper Shelf Energy

Applicability of Miniature C(T) Specimen to Fracture Toughness Evaluation for the Irradiated Japanese Reactor Pressure Vessel Steel

Comparison of Prediction Models for Mechanical Properties of Thermally Aged Cast Austenitic Stainless Steels

Study on Evaluation Procedure for Calculating the Stress Intensity Factor of Flaws Beneath RPV Cladding During Pressurised Thermal Shock Events by FE Analysis

Applicability of Fracture Toughness Curves Developed for Japanese Pressure Vessel Steels to Structural Integrity Evaluation

Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels Against Pressurized Thermal Shock Events in Japan

Applicability of Miniature C(T) Specimen to Evaluation of Fracture Toughness for Reactor Pressure Vessel Steel

Evaluation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock

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

Development of Prediction Equations on Charpy Upper Shelf Energy for Japanese RPV Steels

Simplified J-Integral Evaluation Method for Evaluation of Reactor Pressure Vessel in the Upper-Shelf Region

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