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Norimichi Yamashita
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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
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77601
https://doi.org/10.1115/PVP2009-77601
View Paper titled, Overview of the Revised JEAC4201-2007, Japanese Code of Surveillance Tests for Reactor Vessel Materials
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Topics: Reactor vessels, Surveillance, Embrittlement, Irradiation (Radiation exposure), Nuclear reactors
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
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
Proceedings Papers

Effect of Crack Detection Performance and Sizing Accuracy on Reliability of Piping With Stress Corrosion Cracks

Hideo Machida, Norimichi Yamashita
Proc. ASME. PVP2008, Volume 1: Codes and Standards, 397-404, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61017
https://doi.org/10.1115/PVP2008-61017
View Paper titled, Effect of Crack Detection Performance and Sizing Accuracy on Reliability of Piping With Stress Corrosion Cracks
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Topics: Crack detection, Pipes, Reliability, Stress corrosion cracking, Fracture (Materials), Errors, Fitness-for-service, Boiling water reactors, Failure, Fracture mechanics
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61494
https://doi.org/10.1115/PVP2008-61494
View Paper titled, Master Curve Approach for Some Japanese Reactor Pressure Vessel Steels
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Topics: Reactor vessels, Steel, Fracture toughness, Nuclear power stations
Proceedings Papers

Study on Probabilistic Fracture Mechanics Analysis Codes for Pipes With Stress Corrosion Cracks

Hideo Machida, Manabu Arakawa, Norimichi Yamashita, Shinobu Yoshimura
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 63-70, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48234
https://doi.org/10.1115/ICONE16-48234
View Paper titled, Study on Probabilistic Fracture Mechanics Analysis Codes for Pipes With Stress Corrosion Cracks
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Topics: Fracture mechanics, Pipes, Stress corrosion cracking, Fracture (Materials), Failure, Probability, Reliability, Fitness-for-service, In-service inspection, Leakage
Proceedings Papers

Development of an Inertia-Increased ABWR Internal Pump

Shirou Takahashi, Kousei Umemori, Kooji Shiina, Tetsuya Totani, Akihiro Sakashita, Norimichi Yamashita, Takahisa Kondo
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 725-732, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22344
https://doi.org/10.1115/ICONE10-22344
View Paper titled, Development of an Inertia-Increased ABWR Internal Pump
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Topics: Flywheels, Inertia (Mechanics), Pumps
Proceedings Papers

Evaluation of Flow-Induced Vibration for Fixed Type Guide Rods of Shroud Head and Steam Dryer in ABWR

Shirou Takahashi, Hiroaki Tamako, Tsutomu Kawamura, Kouji Shiina, Masaaki Tsubaki, Akihiro Sakashita, Norimichi Yamashita, Tadashi Narabayashi, Tsuyoshi Hagiwara, Hideo Komita
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 727-734, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22549
https://doi.org/10.1115/ICONE10-22549
View Paper titled, Evaluation of Flow-Induced Vibration for Fixed Type Guide Rods of Shroud Head and Steam Dryer in ABWR
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Topics: Flow-induced vibrations, Nozzles, Rods, Steam
Proceedings Papers

Analytical Evaluation of Unsteady Thermal Hydraulic Characteristics in Shell and Tube Heat Exchangers

Shiro Takahashi, Yuichi Narumi, Kiyoshi Ishihama, Akihito Yokoyama, Toyohiko Tsuge, Masaaki Hayashi, Hidetoshi Takehara, Norimichi Yamashita
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 393-400, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89389
https://doi.org/10.1115/ICONE14-89389
View Paper titled, Analytical Evaluation of Unsteady Thermal Hydraulic Characteristics in Shell and Tube Heat Exchangers
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Topics: Heat exchangers, Shells, Flow (Dynamics), Vortices, Computational fluid dynamics, Eddies (Fluid dynamics), Fluctuations (Physics), Fluids, Nuclear power stations, Reliability
Proceedings Papers

Evaluation Criteria for Alternating Loads Based on Partial Inelastic Analyses

Asao Okamoto, Yasuhiro Ohtake, Norimichi Yamashita
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 57-64, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1222
https://doi.org/10.1115/PVP2002-1222
View Paper titled, Evaluation Criteria for Alternating Loads Based on Partial Inelastic Analyses
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Topics: Inelastic analysis, Stress, Collapse, Finite element analysis, Design, Elastic analysis, Evaluation methods, Stress analysis (Engineering)
Proceedings Papers

Verification of Alternative Criteria for Shakedown Evaluation Using Flat Head Vessel

Seiji Asada, Norimichi Yamashita, Asao Okamoto, Isoharu Nishiguchi
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 17-22, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1217
https://doi.org/10.1115/PVP2002-1217
View Paper titled, Verification of Alternative Criteria for Shakedown Evaluation Using Flat Head Vessel
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Topics: Vessels, Finite element analysis, Stress, Cycles, Evaluation methods, Pressure, Shells, Thermal stresses
Proceedings Papers

Analytical and Numerical Evaluation of the Cyclic Yield Area Criteria for Shakedown Requirements

Isoharu Nishiguchi, Asao Okamoto, Norimichi Yamashita, Mitsuru Aoki
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 39-46, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1220
https://doi.org/10.1115/PVP2002-1220
View Paper titled, Analytical and Numerical Evaluation of the Cyclic Yield Area Criteria for Shakedown Requirements
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Topics: ASME Boiler and Pressure Vessel Code, Elastic analysis, Failure mechanisms, Finite element methods, Finite element model, Stress, Stress analysis (Engineering)
Proceedings Papers

Evaluation of Thermal Stress Ratchet in Plastic FEA

Yukinori Yamamoto, Norimichi Yamashita, Masaaki Tanaka
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 3-10, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1215
https://doi.org/10.1115/PVP2002-1215
View Paper titled, Evaluation of Thermal Stress Ratchet in Plastic FEA
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Topics: Finite element analysis, Thermal stresses, Stress, Cylinders, Pressure, Vessels, Cycles, Temperature distribution, Theoretical analysis, Work hardening
Proceedings Papers

Effects of Local Peak Stress Distribution on the Ratchet Limit

Nobuyoshi Yanagida, Masaaki Tanaka, Norimichi Yamashita, Yukinori Yamamoto
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 11-16, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1216
https://doi.org/10.1115/PVP2002-1216
View Paper titled, Effects of Local Peak Stress Distribution on the Ratchet Limit
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Topics: Stress concentration, Stress, Finite element analysis, Vessels, Pressure, Thermal stresses
Proceedings Papers

Reliability Assessment of Piping in a Nuclear Power Plant Considering Flaw Detection Probability

Hideo Machida, Norimichi Yamashita, Shinobu Yoshimura, Genki Yagawa
Proc. ASME. PVP2004, Pressure Vessel and Piping Codes and Standards, 247-254, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2698
https://doi.org/10.1115/PVP2004-2698
View Paper titled, Reliability Assessment of Piping in a Nuclear Power Plant Considering Flaw Detection Probability
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Topics: Flaw detection, Nuclear power stations, Pipes, Probability, Reliability, Fracture (Materials), Inspection, Boiling water reactors, Cracking (Materials), Failure
Proceedings Papers

Seismic Loads for Crack Stability Assessment in a Review of Lead-Before-Break (LBB) Applicability

Norimichi Yamashita, Hideo Machida, Shinobu Yoshimura, Genki Yagawa
Proc. ASME. PVP2004, Pressure Vessel and Piping Codes and Standards, 365-372, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2714
https://doi.org/10.1115/PVP2004-2714
View Paper titled, Seismic Loads for Crack Stability Assessment in a Review of Lead-Before-Break (LBB) Applicability
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Topics: Fracture (Materials), Stability, Stress, Earthquakes, Coolants, Leakage, Pipes, Design, Crack propagation, Boiling water reactors