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State Variable Description of 316 Stainless Steel Postirradiation Mechanical Properties / GL. Wire

Conference Author
Effects of Radiation on Materials (1980 : Savannah, Georgia)
Physical Description
1 online resource (18 pages) : illustrations, figures, tables
Additional Creators
Wire, GL., American Society for Testing and Materials, and ASTM International
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Summary
An extensive description of mechanical response of breeder reactor core components to transient loading is required for design and safety analysis. This description is needed for strain rates from 10¿̐ư5 to 101/s, test temperatures from 232¿̐ưC to over 1000¿̐ưC, and neutron (n) fluences from 0 to 1.3 ¿̐ư 1023 n/cm2 (E > 0.1 MeV).2 An equation-of-state approach, proposed by Hart, is applied to existing tensile and burst data to develop an improved method of predicting mechanical behavior over this range of temperature and strain rates.
Dates of Publication and/or Sequential Designation
Volume 1981, Issue 725 (January 1981)
Subject(s)
Other Subject(s)
ISBN
0803107552
9780803107557
9780803147942 (e-ISBN)
Digital File Characteristics
text file PDF
Bibliography Note
Includes bibliographical references 19.
Other Forms
Also available in PDF edition.
Also available online via the World Wide Web. Tables of contents and abstracts freely available; full-text articles available by subscription.
Full text article also available for purchase.
Reproduction Note
Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1981. Mode of access: World Wide Web. System requirements: Web browser. Access may be restricted to users at subscribing institutions.
Technical Details
Mode of access: World Wide Web.
Source of Acquisition
ASTM International PDF Purchase price USD25.
View MARC record | catkey: 27987472