Thermal fatigue behavior of thin-walled cylindrical carbon steel specimens in simulated BWR environment-Reference-Cited by-同舟云学术

Thermal fatigue behavior of thin-walled cylindrical carbon steel specimens in simulated BWR environment

Published:1998-08 Issue:1 Volume:184 Page:123-133
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hayashi Makoto

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference7 articles.

1. ASME Pressure Vessel Code, Sec III, Div. 1–Appendix I, 1992.

2. Hayashi, M., Enomoto, K., Iokibe, H., 1987. Proc. Annu. Meet. of the Atomic Energy Society of Japan, Nagoya, p. 41.

3. Hayashi, M., Enomoto, K., Saito, T., et al., 1994. ASME PVP, 287, 81.

4. Hayashi, M., 1995. ASME PVP, 306, 71.

5. Suzuki, S., Ito, S., Iokibe, H., et al., 1987. Proc. Annu. Meet. of the Atomic Energy Society of Japan, Nagoya, p. 38.

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