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Hisamitsu Hatoh
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Proceedings Papers

Development of New Design Fatigue Curves in Japan: Discussion of Effect of Surface Finish on Fatigue Strength of Nuclear Component Materials

Motoki Nakane, Yun Wang, Hisamitsu Hatoh, Masato Yamamoto, Akihiko Hirano, Kentaro Hayashi
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A044, July 14–19, 2019
Paper No: PVP2019-93167
https://doi.org/10.1115/PVP2019-93167
View Paper titled, Development of New Design Fatigue Curves in Japan: Discussion of Effect of Surface Finish on Fatigue Strength of Nuclear Component Materials
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Topics: Design, Fatigue, Fatigue strength, Finishes, Fatigue testing, Surface roughness, Evaluation methods, Carbon steel, Databases, Machining
Proceedings Papers

Development of New Design Fatigue Curves in Japan: Discussion of Best-Fit Curves Based on Fatigue Test Data With Small-Scale Test Specimen

Yun Wang, Hisamitsu Hatoh, Masato Yamamoto, Motoki Nakane, Akihiko Hirano, Kentaro Hayashi
Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A001, July 15–20, 2018
Paper No: PVP2018-84052
https://doi.org/10.1115/PVP2018-84052
View Paper titled, Development of New Design Fatigue Curves in Japan: Discussion of Best-Fit Curves Based on Fatigue Test Data With Small-Scale Test Specimen
Open the PDF for Development of New Design Fatigue Curves in Japan: Discussion of Best-Fit Curves Based on Fatigue Test Data With Small-Scale Test Specimen in another window
Topics: Design, Fatigue, Fatigue testing, Stress, Tensile strength, Alloys, Carbon steel, Fatigue life, Mechanical properties, Nuclear power stations
Proceedings Papers

Field Experience of Water Jet Peening Application on BWR Reactor Internals With Cracked Surfaces

Ren Morinaka, Kunihiro Hasegawa, Masashi Fukaya, Yuji Matsui, Hisamitsu Hatoh, Noboru Saito, Fujio Yoshikubo, Akihiro Kanno
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, 241-250, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55070
https://doi.org/10.1115/ICONE20-POWER2012-55070
View Paper titled, Field Experience of Water Jet Peening Application on BWR Reactor Internals With Cracked Surfaces
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Topics: Boiling water reactors, Shot peening, Water, Fracture (Materials), Nuclear power, Crack propagation, JSME Standards, Nuclear power stations, Nuclear reactors, Stress corrosion cracking
Proceedings Papers

Mitigation of Stress Corrosion Cracking Based on Residual Stress Improvement by Water Jet Peening (WJP)

Masashi Fukaya, Fujio Yoshikubo, Hisamitsu Hatoh, Yuji Matsui, Yoshiaki Tamura, Yoichiro Matsumoto
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 919-926, July 17–21, 2011
Paper No: PVP2011-57493
https://doi.org/10.1115/PVP2011-57493
View Paper titled, Mitigation of Stress Corrosion Cracking Based on Residual Stress Improvement by Water Jet Peening (WJP)
Open the PDF for Mitigation of Stress Corrosion Cracking Based on Residual Stress Improvement by Water Jet Peening (WJP) in another window
Topics: Shot peening, Stress, Stress corrosion cracking, Water, Bubbles, Simulation, Collapse, Pressure, Bubbly flow, Flow (Dynamics)