Development of thermal fatigue testing apparatus with BWR water environment and thermal fatigue strength of austenitic stainless steels-Reference-Cited by-同舟云学术

Development of thermal fatigue testing apparatus with BWR water environment and thermal fatigue strength of austenitic stainless steels

Published:1998-08 Issue:1 Volume:184 Page:113-122
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hayashi Makoto,Enomoto Kunio,Saito Takashi,Miyagawa Toshiharu

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

Reference6 articles.

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

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

3. Hayashi, M., Enomoto, K., 1996. J. Soc. Mater. Sci. Jpn. 45, 1107–1112.

4. Hirano, A., Hayashi, M., Takehara, H., et al., 1993. Proc. 70th JSME Spring Annu. Meet., Tokyo, p. 741.

5. JWES-AE-8103, 1981. Japan Welding Engineering Society, pp. 100–101.

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