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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

Paper No: PVP2010-25514

DOI: https://doi.org/10.1115/PVP2010-25514

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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

Paper No: PVP2009-77658

DOI: https://doi.org/10.1115/PVP2009-77658

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Topics: Embrittlement, Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Atoms, Fluence (Radiation measurement), Neutron flux, Probes, Reactor vessels, Steel

Proceedings Papers

Microstrucutural Characterization of RPV Steels Irradiated to High Fluences

Minoru Tomimatsu, Hiroyuki Sakamoto, Kenji Dohi, Toshiyuki Watanabe, Hiroshi Matsuzawa

Proc. ASME. PVP2009, Volume 1: Codes and Standards, 435-444, July 26–30, 2009

Paper No: PVP2009-78103

DOI: https://doi.org/10.1115/PVP2009-78103

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Topics: Steel, Dislocations, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Base metals, Copper, Density, Electron microscopes, Light water reactors

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

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

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

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

Overview of the Japanese Code of Surveillance Test Program for Reactor Vessels

Minoru Tomimatsu, Seiji Asada, Hitoshi Ohata, Hideo Kobayashi

Proc. ASME. PVP2006-ICPVT-11, Volume 1: Codes and Standards, 443-450, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93785

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93785

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Topics: Reactor vessels, Surveillance, Nuclear reactors, Design, Energy engineering, Inspection, Mechanical properties, Radiation (Physics), Temperature, Vessels

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

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

Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement

Microstrucutural Characterization of RPV Steels Irradiated to High Fluences

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

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

Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels

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

Overview of the Japanese Code of Surveillance Test Program for Reactor Vessels

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

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