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

BRAZING ZIRCALOY FUEL ASSEMBLY COMPONENTS FOR THE CAROLINAS VIRGINIA TUBE REACTOR, CVTR PROJECT. Terminal Report

Technical Report ·
OSTI ID:4003878
Zirconium-- beryllium, zirconium-- beryllium-- iron, and zirconium-- beryllium-- copper brazing alloys were investi gated with respect to corrosion resistance and mechanical strength after joining to Zircaloy components by brazing. The zirconium--beryllium alloys had the best corrosion resistance in 680 deg F neutral, degassed, demineralized water at 2705 psi, and the highest average joint strengths. Alloy powders made by hydriding, crushing in argon, and vacuum degassing had a minimum of hydrogen, oxygen, and nitrogen contamination in the brazing alloy. Brazing temperatures and times at temperature were found to be critical in minimizing brazing alloy penetration into the base metal. Short times at brazing temperatures followed by an 800 deg C diffusion treatment proved to be the most satisfactory method for producing strong, corrosion resistant, reproducible joints without eroding the base metal. Several brazed Zircaloy end rings were used satisfactorily in the CVTR inpile loop and in the CVTR Phase II loop study. (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
NSA Number:
NSA-15-026511
OSTI ID:
4003878
Report Number(s):
CVNA-85
Country of Publication:
United States
Language:
English

Similar Records

FURNACE BRAZING OF ZIRCALOY
Technical Report · Wed Dec 31 23:00:00 EST 1958 · OSTI ID:4162989

EUTECTIC BRAZING OF ZIRCALOY 2 TO TYPE 304 STAINLESS STEEL
Journal Article · Wed Jan 31 23:00:00 EST 1962 · Welding J. (N.Y.) · OSTI ID:4815519

THE STRENGTHENING EFFECT OF BERYLLIUM ON ZIRCALOY-3. Interim Report
Technical Report · Fri Aug 16 00:00:00 EDT 1957 · OSTI ID:4300749