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Journal Articles

Research and Development of Rubber Bearings for Sodium-Cooled Fast Reactor: Ultimate Properties of Half-Scale Thick Rubber Bearings Based on Breaking Tests

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Tsuyoshi Fukasawa, Shigeki Okamura, Tomohiko Yamamoto, Nobuchika Kawasaki, Tsutomu Hirotani, Eriko Moriizumi, Yu Sakurai, Nobuo Masaki
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2018, 140(1): 011401.
Paper No: PVT-16-1160
https://doi.org/10.1115/1.4038435
Published Online: November 30, 2017
View Articletitled, Research and Development of Rubber Bearings for Sodium-Cooled Fast Reactor: Ultimate Properties of Half-Scale Thick Rubber Bearings Based on Breaking Tests
Open the PDF for Research and Development of Rubber Bearings for Sodium-Cooled Fast Reactor: Ultimate Properties of Half-Scale Thick Rubber Bearings Based on Breaking Tests in another window
Topics: Bearings, Design, Rubber, Shear (Mechanics), Stiffness, Stress, Hardening, Sodium fast reactors, Compressive stress
Journal Articles

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

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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 Articletitled, The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor
Open the PDF for The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor in another window
Topics: Base metals, Creep, Rupture, Sodium fast reactors, Steel, Stress, Welded joints, Temperature, Design
Journal Articles

Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

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Takashi Wakai, Hideo Machida, Manabu Arakawa, Shinji Yoshida, Yasuhiro Enuma
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2013, 135(1): 011401.
Paper No: PVT-11-1116
https://doi.org/10.1115/1.4007642
Published Online: December 4, 2012
View Articletitled, Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel
Open the PDF for Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel in another window
Topics: Displacement, Finite element analysis, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Tension, Thin wall structures, Stress, Leak-before-break
Journal Articles

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

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N. Mani, G. Thanigaiyarasu, P. Chellapandi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2012, 134(2): 021211.
https://doi.org/10.1115/1.4005385
Published Online: January 25, 2012
View Articletitled, Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
Open the PDF for Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor in another window
Topics: Boilers, Finite element methods, Fracture (Materials), Junctions, Leakage, Leak-before-break, Nozzles, Shells, Sodium, Sodium fast reactors