Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels / MI. De Vries

Conference Author:: Influence of Radiation on Material Properties: 13th International Symposium (Part II) (13), 2nd : 1986 : Seattle, WA)
Physical Description:: 1 online resource (17 pages) : illustrations, figures, tables
Additional Creators:: De Vries, MI., American Society for Testing and Materials, and ASTM International

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Summary:

Small compact-tension specimens of Type 316 plate and Type 304 forging have been irradiated in the High Flux Reactor (HFR) at Petten, The Netherlands, up to a fluence level of 2 ¿̐ư 1024 neutrons (n) ¿̐ư m¿̐ư2 (E > 0.1 MeV) at 573 K. Post-irradiation fatigue crack propagation tests and J-integral fracture toughness tests have been performed at the irradiation temperature. Additional tests were made at the higher temperatures of 723 and 823 K.

Dates of Publication and/or Sequential Designation:

Volume 1987, Issue 956 (January 1987)

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ISBN:

9780803150171 (e-ISBN)
9780803109636
0803109636

Digital File Characteristics:

text file PDF

Bibliography Note:

Includes bibliographical references 19.

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Also available online via the World Wide Web. Tables of contents and abstracts freely available; full-text articles available by subscription.
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Also available in PDF edition.

Reproduction Note:

Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1987. Mode of access: World Wide Web. System requirements: Web browser. Access may be restricted to users at subscribing institutions.

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Mode of access: World Wide Web.

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ASTM International PDF Purchase price USD25.

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