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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

DOI: https://doi.org/10.1115/PVP2020-21698

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Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Notch testing, Phase transition temperature, Reactor vessels, Statistics, Steel, Uncertainty

Proceedings Papers

Study on a New Design Fatigue Evaluation Method

Seiji Asada, Takashi Hirano, Takehiko Sera

Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A029, July 19–23, 2015

Paper No: PVP2015-45089

DOI: https://doi.org/10.1115/PVP2015-45089

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Topics: Design, Evaluation methods, Fatigue, Fatigue design, Stress, Alloy steel, Carbon steel, Nuclear power, Stainless steel, Welding

Proceedings Papers

Evaluation of SCC Crack Growth Rate in BWR Water Based on Elastic-Plastic Fracture Mechanics Parameters

Masahiro Takanashi, Yu Itabashi, Takashi Hirano

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A077, July 19–23, 2015

Paper No: PVP2015-45759

DOI: https://doi.org/10.1115/PVP2015-45759

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Topics: Boiling water reactors, Fracture (Materials), Fracture mechanics, Water, Stress, Deformation, Stress corrosion cracking, Welding

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

Study on Validity of Stress Intensity Factor in CT Specimen for Materials With Low Yield Stress

Masahiro Takanashi, Yu Itabashi, Takashi Hirano

Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A016, July 14–18, 2013

Paper No: PVP2013-97953

DOI: https://doi.org/10.1115/PVP2013-97953

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Topics: Stress, Yield stress, Fracture mechanics, Alloys, Finite element analysis, Flow (Dynamics), Regulations, Steel, Tension, Testing

Proceedings Papers

Stress Corrosion Cracking Behavior Around Interface Between Nickel Base Alloy (Alloy182) and Low-Alloy Steel

Yu Itabashi, Yohei Sakakibara, Masahiro Takanashi, Guen Nakayama, Takashi Hirano

Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 573-582, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55266

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55266

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Topics: Alloys, Nickel, Steel, Stress corrosion cracking, Fracture (Materials), Stress, Water, Electrical conductivity, Light water reactors, Coolants

Proceedings Papers

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: First Round Robin Test on Uniform Specimens of Reactor Pressure Vessel Material

Masato Yamamoto, Akihiko Kimura, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Atsushi Chiba, Takashi Hirano, Takuji Sugihara, Masanari Sugiyama, Naoki Miura, Naoki Soneda

Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 73-79, July 15–19, 2012

Paper No: PVP2012-78661

DOI: https://doi.org/10.1115/PVP2012-78661

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Topics: ASTM International, Cracking (Materials), Dimensions, Evaluation methods, Fracture (Process), Fracture toughness, Governments, Machining, Reactor vessels, Reliability

Proceedings Papers

Overview of Code Case on Alternative Design Methodology by Using Elastic-Plastic Finite Element Analysis for Class 1 Vessels in the JSME Rules on Design and Construction

Seiji Asada, Takashi Hirano, Tetsuya Nagata, Naoto Kasahara

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 577-584, July 18–22, 2010

Paper No: PVP2010-25525

DOI: https://doi.org/10.1115/PVP2010-25525

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Topics: Construction, Design, Design methodology, Finite element analysis, Japan Society of Mechanical Engineers, Vessels, Stress, Collapse, Evaluation methods, Elastic analysis

Proceedings Papers

Overview of the Revised JEAC4201-2007, Japanese Code of Surveillance Tests for Reactor Vessel Materials

Takashi Hirano, Seiji Asada, Norimichi Yamashita, Masanobu Iwasaki, Minoru Tomimatsu

Proc. ASME. PVP2009, Volume 1: Codes and Standards, 387-394, July 26–30, 2009

Paper No: PVP2009-77601

DOI: https://doi.org/10.1115/PVP2009-77601

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Topics: Reactor vessels, Surveillance, Embrittlement, Irradiation (Radiation exposure), Nuclear reactors

Proceedings Papers

Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels

Minoru Tomimatsu, Takashi Hirano, Seiji Asada, Ryoichi Saeki, Naoki Miura, Norimichi Yamashita, Akira Yonehara, Itaru Saito

Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 855-862, July 27–31, 2008

Paper No: PVP2008-61494

DOI: https://doi.org/10.1115/PVP2008-61494

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Topics: Reactor vessels, Steel, Fracture toughness, Nuclear power stations

Proceedings Papers

Incorporation of the New Irradiation Embrittlement Correlation Method Into the Japanese Code of Surveillance Tests for Reactor Vessel Materials

Seiji Asada, Takashi Hirano, Naoki Soneda, Norimichi Yamashita, Akira Yonehara, Minoru Tomimatsu

Proc. ASME. PVP2008, Volume 1: Codes and Standards, 571-579, July 27–31, 2008

Paper No: PVP2008-61492

DOI: https://doi.org/10.1115/PVP2008-61492

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Topics: Embrittlement, Irradiation (Radiation exposure), Reactor vessels, Surveillance, Boiling water reactors, Electricity (Physics), Nuclear reactors, Pressurized water reactors

Proceedings Papers

Application of Magnetic Stir Welding to Dissimilar Metal Structural Weld Overlay

Takeshi Yoshida, Takaaki Matsuoka, Yuta Uchida, Takashi Hirano

Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 539-546, May 11–15, 2008

Paper No: ICONE16-48319

DOI: https://doi.org/10.1115/ICONE16-48319

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Topics: Metals, Overlays (Materials engineering), Welding, Municipal solid wastes, Alloys, Fracture (Materials), Stainless steel, Sulfur, Welded joints, Base metals

Proceedings Papers

Development of Residual Stress Improvement for Nuclear Pressure Vessel Instrumentation Nozzle Weld Joint (P-43+P-8) by Means of Induction Heating

Takuro Terajima, Takashi Hirano

Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 467-476, July 17–20, 2006

Paper No: ICONE14-89297

DOI: https://doi.org/10.1115/ICONE14-89297

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Topics: Alloys, Electromagnetic induction, Heating, Instrumentation, Iron, Nickel, Nozzles, Reactor vessels, Stainless steel, Stress

Proceedings Papers

Evaluation of Fatigue Damage on Operating Plant Components in LWR Water

Makoto Higuchi, Takashi Hirano, Katsumi Sakaguchi

Proc. ASME. PVP2004, Pressure Vessel and Piping Codes and Standards, 129-138, July 25–29, 2004

Paper No: PVP2004-2682

DOI: https://doi.org/10.1115/PVP2004-2682

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Topics: Fatigue damage, Light water reactors, Water, Temperature, Fatigue, Cycles, Stress, Transients (Dynamics), Alloys, Carbon

Proceedings Papers

Application of the Master Curve Method to the Japanese RPV Materials

Hiroomi Funakoshi, Yasushi Kanazawa, Takashi Hirano, Naoki Kojima, Kouichi Matsumoto, Naoki Soneda, Naoki Miura

Proc. ASME. PVP2005, Volume 3: Design and Analysis, 339-346, July 17–21, 2005

Paper No: PVP2005-71629

DOI: https://doi.org/10.1115/PVP2005-71629

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Topics: ASTM International, Boiling water reactors, Fracture toughness, Reactor vessels, Steel, Surveillance, Switches

Proceedings Papers

Overview of the JEA Code of Fracture Toughness Requirements for Nuclear Power Plant Components

Minoru Tomimatsu, Seiji Asada, Takashi Hirano, Hideo Kobayashi

Proc. ASME. PVP2006-ICPVT-11, Volume 1: Codes and Standards, 451-457, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93786

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93786

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Topics: Fracture toughness, Nuclear power stations, Reactor vessels, Temperature, Acceptance criteria, Energy engineering, Evaluation methods, Inspection, Pressure, Thermal shock

Journal citation

NARROW

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

Study on a New Design Fatigue Evaluation Method

Evaluation of SCC Crack Growth Rate in BWR Water Based on Elastic-Plastic Fracture Mechanics Parameters

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

Study on Validity of Stress Intensity Factor in CT Specimen for Materials With Low Yield Stress

Stress Corrosion Cracking Behavior Around Interface Between Nickel Base Alloy (Alloy182) and Low-Alloy Steel

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: First Round Robin Test on Uniform Specimens of Reactor Pressure Vessel Material

Overview of Code Case on Alternative Design Methodology by Using Elastic-Plastic Finite Element Analysis for Class 1 Vessels in the JSME Rules on Design and Construction

Overview of the Revised JEAC4201-2007, Japanese Code of Surveillance Tests for Reactor Vessel Materials

Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels

Incorporation of the New Irradiation Embrittlement Correlation Method Into the Japanese Code of Surveillance Tests for Reactor Vessel Materials

Application of Magnetic Stir Welding to Dissimilar Metal Structural Weld Overlay

Development of Residual Stress Improvement for Nuclear Pressure Vessel Instrumentation Nozzle Weld Joint (P-43+P-8) by Means of Induction Heating

Evaluation of Fatigue Damage on Operating Plant Components in LWR Water

Application of the Master Curve Method to the Japanese RPV Materials

Overview of the JEA Code of Fracture Toughness Requirements for Nuclear Power Plant Components

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