Fatigue and creep-fatigue tests at elevated temperature were conducted on two different-sized bellows, φ 1100 mm and φ 300 mm in nominal inner diameter, to investigate the fatigue life and the creep-fatigue interaction in a bellows, and also to provide test data for developing a life prediction method and design-by-analysis rules for bellows in elevated temperature service. A series of tests consisted of strain behavior and fatigue tests at room temperature, and fatigue and creep-fatigue tests at elevated temperature. Also, inelastic finite element analyses were performed on a bellows under internal pressure and cyclic axial deflections. Analytical results were compared with the measured data obtained in the room temperature testing to verify the strain prediction method.
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August 1988
Research Papers
Fatigue and Creep-Fatigue Testing of Bellows at Elevated Temperature
S. Yamamoto,
S. Yamamoto
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
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K. Isobe,
K. Isobe
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
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S. Ohte,
S. Ohte
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
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N. Tanaka,
N. Tanaka
Nuclear Engineering Laboratory, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
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S. Ozaki,
S. Ozaki
Nuclear Engineering Laboratory, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
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K. Kimura
K. Kimura
Advanced Reactor Engineering Department, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
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S. Yamamoto
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
K. Isobe
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
S. Ohte
Mechanical Engineering Laboratory, Research and Development Center, Toshiba Corporation, Kawasaki, Japan
N. Tanaka
Nuclear Engineering Laboratory, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
S. Ozaki
Nuclear Engineering Laboratory, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
K. Kimura
Advanced Reactor Engineering Department, Nuclear Energy Group, Toshiba Corporation, Kawasaki, Japan
J. Pressure Vessel Technol. Aug 1988, 110(3): 301-307 (7 pages)
Published Online: August 1, 1988
Article history
Received:
April 19, 1988
Online:
November 5, 2009
Citation
Yamamoto, S., Isobe, K., Ohte, S., Tanaka, N., Ozaki, S., and Kimura, K. (August 1, 1988). "Fatigue and Creep-Fatigue Testing of Bellows at Elevated Temperature." ASME. J. Pressure Vessel Technol. August 1988; 110(3): 301–307. https://doi.org/10.1115/1.3265603
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