Miniaturized fatigue crack growth specimen technology and results-Reference-Cited by-同舟云学术

Miniaturized fatigue crack growth specimen technology and results

Published:1981-01 Issue: Volume:104 Page:1501-1504
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Puigh R.J.,Bauer R.E.,Ermi A.M.,Chin B.A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference10 articles.

1. Michel, D. J., Irradiation Effects on fatigue Crack Propagation in Austenitic Stainless Steels, NRL Memorandum Report 3610, 1–22.

2. Effects of Neutron Irradiation of Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures;Shahinian;ASTM STP,1973

3. The Effect of Fast Neutron Irradiation Upon the Fatigue-Crack Propagation Behavior of Two Austenitic Stainless Steels;James;J. Nucl. Mat.,1976

4. Miniature Specimen Technology for Postirradiation Fatigue Crack Growth Testing;Mervyn,1979

5. Assessment of Titanium for Use in the First Wall/ Blanket Structure of Fusion Power Reactors;Davis;Electric Power Research Institute, EPRI-836 (Project 472-1),1977

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