Relationship between hardness and flow stress of ordered Zr/sub 3/Al polycrystals

Journal Article · Tue Feb 01 04:00:00 EST 1977 · Metall. Trans., A; (United States)

DOI:https://doi.org/10.1007/BF02661657· OSTI ID:6431131

Schulson, E M; Roy, J A

A relationship between hardness and flow stress for the ordered L1/sub 2/ phase Zr/sub 3/Al, a possible structural material for use in nuclear power reactors, is described. The test material was Zr-8.9 wt pct Al prepared from crystal-bar zirconium and aluminum of 99.999 pct purity by nonconsumable arc -melting. Buttons were sealed in Zircaloy-2 fuel sheathing and then hot-rolled at 1325/sup 0/K to 5 mm strip. To effect both the peritectoid transformation to form Zr/sub 3/Al, described previously, and grain growth, to be described separately, the rolled strip was annealed at a reduced pressure of < 2.6 x 10/sup -4/ Pa at temperatures between 1075 and 1260/sup 0/K for times from 2 to 1000 h. In this condition, the matrix was Zr/sub 3/Al which contained < 1 pct residual ..cap alpha..-Zr and Zr/sub 2/Al.

• Research Organization: Chalk River Nuclear Labs, Ontario, Canada
• OSTI ID: 6431131
• Journal Information: Metall. Trans., A; (United States), Journal Name: Metall. Trans., A; (United States) Vol. 8A; ISSN MTTAB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components &amp; Accessories
36 MATERIALS SCIENCE
360103* -- Metals &amp; Alloys-- Mechanical Properties
ALLOYS
ALUMINIUM ALLOYS
HARDNESS
LATTICE PARAMETERS
MECHANICAL PROPERTIES
REACTOR MATERIALS
STRESSES
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS