Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

PREFERRED ORIENTATION IN ZIRCONIUM ALLOY WIRE FUEL ELEMENTS

Technical Report ·
OSTI ID:4160662

Texture determinations were made of the claddings and cores of wire fuel elements consisting of either 3 or 5% Zr-Sn cladding on cores of 20% U - Zr. Results are given for specimens worked at various temperatures from 600 to 900 deg C and subjected to reductions of area from 59 to 97%. A single (1010) fiber texture was found in the cladding after hot swaging. Recrystallization abcve the swaging temperature produced a duplex (101-bar0) (112-bar0) fiber texture. A beta heat treatment appeared to randomize the texture. The texture of the alpha -Zr phase in the core corresponded to that predicted by assuming the conventional BCC fiber texture and applying Burger's transformation mechanism for zirconium. The orientation study of the epsilon phase in the core was somewhat questionable. Tentative results indicated a (101) fiber texture for this phase in the "as hotswaged" condition. (auth)

Research Organization:
Sylvania Electric Products Inc. Atomic Energy Div., Bayside, N.Y.
NSA Number:
NSA-14-022033
OSTI ID:
4160662
Report Number(s):
SEP-111; DCF-4287
Country of Publication:
United States
Language:
English

Similar Records

Preferred orientation in extruded magnesium compacts
Journal Article · Fri Feb 01 00:00:00 EDT 1974 · J. Nucl. Mater., v. 50, no. 1, pp. 98-102 · OSTI ID:4309430

PREFERRED ORIENTATION IN THORIUM
Technical Report · Fri Oct 30 23:00:00 EST 1959 · OSTI ID:4250052

DEFORMATION MODES OF ZIRCONIUM AT 77, 575, AND 1075 K
Journal Article · Sat Oct 01 00:00:00 EDT 1960 · Trans. Met. Soc. AIME · OSTI ID:4156895