Development of Fuel Cladding for Fast Reactors / G. W. Cunningham
- Conference Author:
- Irradiation Effects in Structural Alloys for Thermal and Fast Reactors (1968 : San Francisco, Calif.)
- Physical Description:
- 1 online resource (7 pages) : illustrations, figures, tables
- Additional Creators:
- Cunningham, G. W., American Society for Testing and Materials, and ASTM International
- Restrictions on Access:
- Subscription required for access to full text.
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- The U. S. Atomic Energy Commission is conducting an extensive program directed toward the development of thin-wall small diameter tubing that can remain in the fast reactor environment for periods up to three years at temperatures to 800 C, strains to 3 percent, and a total fluence of 3 ¿̐ư 10 23 nvt. Austenitic stainless steels have been selected as the reference material with vanadium alloys as the primary backup material. Emphasis has been placed upon quality assurance for commercially produced stainless tubing. The experimental program also includes extensive work on sodium corrosion and radiation damage.
- Dates of Publication and/or Sequential Designation:
- Volume 1969, Issue 457 (January 1969)
- Other Subject(s):
- 9780803160361 (e-ISBN)
- Digital File Characteristics:
- text file PDF
- Bibliography Note:
- Includes bibliographical references.
- 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, 1969. 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: 28002469