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Accelerated Irradiation Growth of Zirconium Alloys / M. Griffiths, RW. Gilbert, V. Fidleris

Conference Author
Zirconium in the Nuclear Industry: Eighth International Symposium (8th : 1988 : San Diego, CA)
Physical Description
1 online resource (20 pages) : illustrations, figures, tables
Additional Creators
Griffiths, M., Gilbert, RW., Fidleris, V., American Society for Testing and Materials, and ASTM International
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Summary
Sponge zirconium and Zr-2.5 wt% Nb, Zircaloy, or Excel alloys all exhibit accelerated irradiation growth compared with high-purity crystal-bar zirconium for irradiation temperatures between 550 to 710 K and fluences between 0.1 to 10 ¿̐ư 1025 n ¿̐ư m-2 (E > 1 MeV). There is generally an incubation period or fluence before the onset of accelerated or ¿̐ưbreakaway¿̐ư growth, which is dependent on the particular material being irradiated, its metallurgical condition before irradiation, and the irradiation temperature.
Dates of Publication and/or Sequential Designation
Volume 1989, Issue 1023 (January 1989)
Subject(s)
Other Subject(s)
ISBN
9780803150843 (e-ISBN)
9780803111998
0803111991
Digital File Characteristics
text file PDF
Bibliography Note
Includes bibliographical references 26.
Other Forms
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.
Also available in PDF edition.
Reproduction Note
Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1989. 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.
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