POWER REACTOR PROGRAM. Progress Report to E. I. du Pont de Nemours and Company for the Period January 1, 1959 through January 31, 1959

Technical Report · Thu Feb 26 04:00:00 EST 1959

OSTI ID:4292861

Gardner, F S; Richmond, W J; Larson, W L; Huntress, A M; Kaufmann, A R; Kaufman, D F; Jenkins, R G; Lumbert, A R; Loewenstein, P; Pemsler, J P; Isserow, S

Processing, fabricating, and testing of reactor fuel tubes are described. Comparative costs for extruding and cupping of Zircaloy-2 are given along with a complete fabricating procedure for this process change. Improvement of nondestructive testing apparatus for clad thickness was directed to existing equipment including standards, resolution, and temperature characteristics. A short 800 deg c heat treatment for Zircaloy-2 clad U--2 wt.% Zr tubes is being studied as an economical replacement of the diffusion heat treatment. Develop mental melting of 90.6 wt.% Zr--U alloy for casting into cores for driver tube extrusion billets included trials of vacuum induction melting in graphite and one arc melt by the consumable electrode process. The coextruded flat ribbon of Zircaloy-2 clad U--2 wt.% Zr alloy was sectioned and examined for clad thickness along the extrusion length and around the perimeter at several locations. Irradiation behavior of the U--Zr alloy is being studied. (See also NMI-4382.) (W.D.M.)

• Research Organization: Nuclear Metals, Inc., Concord, Mass.
• NSA Number: NSA-13-008934
• OSTI ID: 4292861
• Report Number(s): NMI-4385
• Country of Publication: United States
• Language: English

Related Subjects

CANNING
CASTING
CONFIGURATION
ECONOMICS
EFFICIENCY
ELECTRIC ARCS
ELECTRODES
EXTRUSION
FABRICATION
FUEL ELEMENTS
GRAPHITE
HEAT TREATMENTS
HIGH TEMPERATURE
INDUCTION
MATERIALS TESTING
MELTING
METALLURGY AND CERAMICS
POWER PLANTS
RADIATION EFFECTS
RESOLUTION
STANDARDS
TEMPERATURE
THICKNESS
TUBES
VACUUM
ZIRCALOY