POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period April 1, 1959 through April 30, 1959
The heat treatment of Zircaloy-2 clad power tubes in their copper extrusion Jackets is discussed. The extrusion of unalloyed U from six billets is described. The mechanics of beta treatment of extruded tubes in a vertical salt bath were worked out with the aid of a dummy Cu--10 wt.% Ni tube of power tube dimensions. Measurements on the prototype driver tubes indicate that dimensional tolerances can be met in the extruded condition. An attempt is being made to determine the cause of anomalous corrosion behavior of Zr--0.6 wt.%. Ni alloys arc melted from Zr sponge. A program is reported on-the preparation of slightly enriched U--2% Zr core, Zircaloy-clad tube for irradiation in the Vallecitos test reactor. (W.J.H.)
- Research Organization:
- Nuclear Metals, Inc., Concord, Mass.
- NSA Number:
- NSA-13-020170
- OSTI ID:
- 4246864
- Report Number(s):
- NMI-4393
- Country of Publication:
- United States
- Language:
- English
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POWER REACTOR PROGRAM PROGRESS REPORT TO E.I. DU PONT DE NEMOURS AND COMPANY FOR THE PERIOD MAY 1, 1959 THROUGH MAY 31, 1959
POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period October 1, 1959 through October 31, 1959
Related Subjects
COPPER ALLOYS
CORROSION
ELECTRIC ARCS
ENRICHMENT
EXTRUSION
HEAT TREATMENTS
IRRADIATION
JACKETS
MATERIALS TESTING
MEASURED VALUES
MELTING
METALLURGY AND CERAMICS
NICKEL ALLOYS
POWER PLANTS
PREPARATION
REACTORS
RODS
SALTS
STANDARDS
TUBES
URANIUM
URANIUM ALLOYS
ZIRCALOY
ZIRCONIUM
ZIRCONIUM ALLOYS