SYMPOSIA PAPER Published: 01 January 1969

Development of Fuel Cladding for Fast Reactors


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 × 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.

Author Information

Cunningham, G., W.
U. S. Atomic Energy Commission.
Price: $25.00
Contact Sales
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Developed by Committee: E10
Pages: 329–335
DOI: 10.1520/STP41854S
ISBN-EB: 978-0-8031-6036-1
ISBN-13: 978-0-8031-6190-0