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Kenichiro Satoh
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Journal Articles

The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor

Takuya Yamashita, Takashi Wakai, Takashi Onizawa, Kenichiro Satoh, Kenji Yamamoto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2016, 138(6): 061403.
Paper No: PVT-15-1260
https://doi.org/10.1115/1.4034017
Published Online: September 2, 2016
View Article titled, The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor
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Topics: Base metals, Creep, Rupture, Sodium fast reactors, Steel, Stress, Welded joints, Temperature, Design
Journal Articles

Strength of 316FR Joints Welded by Type 316FR/16-8-2 Filler Metals

Takuya Yamashita, Yuji Nagae, Kenichiro Satoh, Kenji Yamamoto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. April 2016, 138(2): 024501.
Paper No: PVT-15-1033
https://doi.org/10.1115/1.4031444
Published Online: October 6, 2015
View Article titled, Strength of 316FR Joints Welded by Type 316FR/16-8-2 Filler Metals
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Topics: Creep, Filler metals, Welded joints, Welding, Tensile strength, Ferrites (Magnetic materials), Metals, Base metals, Gas tungsten arc welding
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (6) Design Margin Assessment for the New Materials to the Rules

Masanori Ando, Sota Watanabe, Koichi Kikuchi, Tomomi Otani, Kenichiro Satoh, Kazuyuki Tsukimori, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A040, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97803
https://doi.org/10.1115/PVP2013-97803
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (6) Design Margin Assessment for the New Materials to the Rules
Open the PDF for Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (6) Design Margin Assessment for the New Materials to the Rules in another window
Topics: Construction, Design, Fast neutron reactors, JSME Standards, Japan Society of Mechanical Engineers, Creep, Damage, Fatigue, Finite element analysis, Materials properties
Proceedings Papers

A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)

Takashi Wakai, Takashi Onizawa, Takehiko Kato, Shingo Date, Koichi Kikuchi, Kenichiro Satoh
Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A105, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97091
https://doi.org/10.1115/PVP2013-97091
View Paper titled, A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)
Open the PDF for A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR) in another window
Topics: Sodium fast reactors, Steel, Welded joints, Creep, Rupture, Stress, Base metals, Design, Temperature, Damage
Proceedings Papers

A Study on Fatigue and Creep-Fatigue Life Assessment Using Cyclic Thermal Tests With Mod.9Cr-1Mo Steel Structures

Masanori Ando, Hiroshi Kanasaki, Shingo Date, Koichi Kikuchi, Kenichiro Satoh, Hideki Takasho, Kazuyuki Tsukimori
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 327-336, July 15–19, 2012
Publisher: American Society of Mechanical Engineers
Paper No: PVP2012-78402
https://doi.org/10.1115/PVP2012-78402
View Paper titled, A Study on Fatigue and Creep-Fatigue Life Assessment Using Cyclic Thermal Tests With Mod.9Cr-1Mo Steel Structures
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Topics: Creep, Fatigue, Steel, Finite element analysis, Failure, Fracture (Materials), Temperature, Temperature distribution, Cooling, Cycles
Proceedings Papers

Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels

Naoto Kasahara, Kenichiro Satoh, Kazuyuki Tsukimori, Nobuchika Kawasaki
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 315-322, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25414
https://doi.org/10.1115/PVP2010-25414
View Paper titled, Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels
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Topics: Fast neutron reactors, High temperature, Structural design, Vessels, Design, Creep, Reactor vessels, Stress, Fatigue, Modeling
Proceedings Papers

Study on Micro-Mechanism of Base-Triggered Vapor Explosion

Takahiro Arai, Yutaka Abe, Kenichiro Satoh, Yuji Nakagawa
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 873-881, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49594
https://doi.org/10.1115/ICONE12-49594
View Paper titled, Study on Micro-Mechanism of Base-Triggered Vapor Explosion
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Topics: Explosions, Micromechanical devices, Vapors, Water, Accidents, High temperature, Nuclear reactors, Pressure, Shapes