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eBook Chapter

Perspective on Trend Curve Models and Their Role in RPV Integrity

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2023
ISBN: 978-0-8031-7741-3
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eBook Chapter

Surveillance Program for Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7651-5
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Proceedings Papers

MAI Benchmark Campaign of International Software for Reactor Pressure Vessel Integrity Assessment

Emilie Dautreme, Emmanuel Remy, Roman Sueur, Jean-Philippe Fontes, Karine Aubert, Naoki Soneda, Masato Yamamoto, Tim Hardin, Ron Gamble
Proc. ASME. PVP2014, Volume 7: Operations, Applications and Components, V007T07A011, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28212
https://doi.org/10.1115/PVP2014-28212
View Paper titled, MAI Benchmark Campaign of International Software for Reactor Pressure Vessel Integrity Assessment
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Topics: Computer software, Reactor vessels, Probability, Failure, Pressure vessels, Pressurized water reactors, Algorithms, Engineers, Fracture (Materials), Fracture mechanics
Proceedings Papers

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions

Masato Yamamoto, Akihiko Kimura, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Yasuhiro Mabuchi, Hans-Werner Viehrig, Naoki Miura, Naoki Soneda
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A098, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28898
https://doi.org/10.1115/PVP2014-28898
View Paper titled, A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions
Open the PDF for A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions in another window
Topics: Temperature, Fracture toughness, Testing, Electromagnetic scattering, Machinery, Steel, Surveillance, ASTM International, Dimensions, Reliability
Proceedings Papers

High Fluence Surveillance Data and Recalibration of RPV Embrittlement Correlation Method in Japan

Naoki Soneda, Kenichi Nakashima, Kenji Nishida, Kenji Dohi
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A047, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-98076
https://doi.org/10.1115/PVP2013-98076
View Paper titled, High Fluence Surveillance Data and Recalibration of RPV Embrittlement Correlation Method in Japan
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Topics: Embrittlement, Fluence (Radiation measurement), Surveillance, Steel, Databases, Irradiation (Radiation exposure), Neutrons, Reactor vessels
Journal Articles

Rational Determination of Lower-Bound Fracture Toughness Curves Using Master Curve Approach

Naoki Miura, Naoki Soneda, Shu Sawai, Shinsuke Sakai
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2013, 135(6): 061211.
Paper No: PVT-13-1020
https://doi.org/10.1115/1.4025088
Published Online: October 10, 2013
View Article titled, Rational Determination of Lower-Bound Fracture Toughness Curves Using Master Curve Approach
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Topics: Fracture toughness, Temperature, ASTM International
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2012-78661
https://doi.org/10.1115/PVP2012-78661
View Paper titled, 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
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Topics: ASTM International, Cracking (Materials), Dimensions, Evaluation methods, Fracture (Process), Fracture toughness, Governments, Machining, Reactor vessels, Reliability
Journal Articles

Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

Naoki Miura, Naoki Soneda
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2012, 134(2): 021402.
https://doi.org/10.1115/1.4005390
Published Online: January 11, 2012
View Article titled, Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens
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Topics: Fracture toughness, Temperature, ASTM International, Steel
Proceedings Papers

Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens

Naoki Miura, Naoki Soneda
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 593-602, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25862
https://doi.org/10.1115/PVP2010-25862
View Paper titled, Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens
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Topics: Fracture toughness, Temperature, Steel, ASTM International, Surveillance, Ductile-brittle transition, Electromagnetic scattering, Evaluation methods, Forging, Reactor vessels
Proceedings Papers

Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement

Naoki Soneda, Kenji Nishida, Kenji Dohi, Akiyoshi Nomoto, William L. Server, Milan Brumovsky, Milos Kytka, Jack Spanner
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 119-124, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25636
https://doi.org/10.1115/PVP2010-25636
View Paper titled, Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Copper, Mechanical properties, Atoms, Fluence (Radiation measurement), Steel, Fracture toughness, Metals
Proceedings Papers

Effect of Neutron Flux at High Fluence on Microstructural and Hardness Changes of RPV Steels

Kenji Dohi, Kenji Nishida, Akiyoshi Nomoto, Naoki Soneda, Hiroshi Matsuzawa, Minoru Tomimatsu
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 95-102, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25514
https://doi.org/10.1115/PVP2010-25514
View Paper titled, Effect of Neutron Flux at High Fluence on Microstructural and Hardness Changes of RPV Steels
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Topics: Fluence (Radiation measurement), Neutron flux, Steel, Neutrons, Atoms, Irradiation (Radiation exposure), Copper, Flux (Metallurgy), Probes, Reactor vessels
Proceedings Papers

Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement

Kenji Dohi, Kenji Nishida, Akiyoshi Nomoto, Naoki Soneda, Hiroshi Matsuzawa, Minoru Tomimatsu
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 403-409, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77658
https://doi.org/10.1115/PVP2009-77658
View Paper titled, Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement
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Topics: Embrittlement, Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Atoms, Fluence (Radiation measurement), Neutron flux, Probes, Reactor vessels, Steel
Proceedings Papers

Proposal of Rational Determination of Fracture Toughness Lower-Bound Curves by Master Curve Approach

Naoki Miura, Naoki Soneda, Shu Sawai, Shinsuke Sakai
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 367-375, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77360
https://doi.org/10.1115/PVP2009-77360
View Paper titled, Proposal of Rational Determination of Fracture Toughness Lower-Bound Curves by Master Curve Approach
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Topics: Fracture toughness, ASTM International, Temperature, Databases, Ductile-brittle transition, Reliability, Steel, Surveillance
Journal Articles

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Norimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, Naoki Soneda
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102919.
https://doi.org/10.1115/1.4001057
Published Online: July 9, 2010
View Article titled, Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Surveillance, Steel, Reactor vessels
Journal Articles

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Naoki Soneda, Akiyoshi Nomoto
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102918.
https://doi.org/10.1115/1.4001056
Published Online: July 9, 2010
View Article titled, Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
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Topics: Embrittlement, Reactor vessels, Steel, Surveillance, Copper, Irradiation (Radiation exposure), Phase transition temperature, Nickel
Journal Articles

Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall

William Server, Milan Brumovský, Milos Kytka, Naoki Soneda, Jack Spanner
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. May 2010, 7(5): 1–11.
https://doi.org/10.1520/JAI102070
Published Online: May 1, 2010
View Article titled, Further Results on Attenuation of Neutron Embrittlement Effects in a Simulated RPV Wall
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Proceedings Papers

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Naoki Soneda, Akiyoshi Nomoto
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 423-430, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75320
https://doi.org/10.1115/ICONE17-75320
View Paper titled, Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
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Topics: Embrittlement, Reactor vessels, Steel, Surveillance, Irradiation (Radiation exposure), Light water reactors, Mechanical properties, Neutrons, Phase transition temperature, Public utilities
Proceedings Papers

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels in Japan

Norimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, Naoki Soneda
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 431-439, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75322
https://doi.org/10.1115/ICONE17-75322
View Paper titled, Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels in Japan
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel, Surveillance, Boiling water reactors, Electromagnetic scattering, Fracture toughness, Nuclear power stations
Journal Articles

Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials

Naoki Soneda, Kenji Dohi, Akiyoshi Nomoto, Kenji Nishida, Shiori Ishino
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. March 2010, 7(3): 1–20.
https://doi.org/10.1520/JAI102127
Published Online: February 25, 2010
View Article titled, Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61492
https://doi.org/10.1115/PVP2008-61492
View Paper titled, Incorporation of the New Irradiation Embrittlement Correlation Method Into the Japanese Code of Surveillance Tests for Reactor Vessel Materials
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Topics: Embrittlement, Irradiation (Radiation exposure), Reactor vessels, Surveillance, Boiling water reactors, Electricity (Physics), Nuclear reactors, Pressurized water reactors