POWER REACTOR PROGRAM. Progress Report to Savannah River Operations Office, United States Atomic Energy Commission for the Period October 1, 1961-October 31, 1961

Technical Report · Fri Dec 01 04:00:00 EST 1961

OSTI ID:4787237

Isserow, S; Anderson, R W; Jordan, E F; Richmond, W J; Larson, W L

Three tubes, fabricated with 60 mils of cladding for the restraint program, were autoradiographed. In the absence of 60-mil standards, quantitative cladding thickness measurements were not possible. However, comparison with a 30.5-mil standard and with the uniform core sections indicated that the claddings are everywhere greater than 30.5 mils and that there are no abnormally thin bands. The Surfaces of the U --0.3 wt% Al--0.5 wt % Si experimental tube (No. 135) were inspected after the first etch. No serious defects were found. Further processing of the tube is being deferred until the large autoclave becomes available. For chemically recessing the HWCTR tube ends for end cap brazing, three methods, differing in orientation of the tube, are being evaluated. All methods have produced on the Zircaloy surfaces a black layer that retards wetting by the brazing alloy; means are being sought to avoid or to remove this layer. (auth)

• Research Organization: Nuclear Metals, Inc., Concord, Mass.
• NSA Number: NSA-16-012747
• OSTI ID: 4787237
• Report Number(s): NMI-7244
• Country of Publication: United States
• Language: English

Related Subjects

ALLOYS
ALUMINUM ALLOYS
BRAZING
CANNING
CHEMICAL REACTIONS
COATING
COOLANT LOOPS
DEFECTS
FABRICATION
FAILURES
FUEL CANS
FUEL ELEMENTS
HWCTR
MATERIALS TESTING
MEASURED VALUES
POWER PLANTS
RADIOAUTOGRAPHY
REACTOR TECHNOLOGY
SILICON
STANDARDS
SURFACES
THICKNESS
TUBES
URANIUM ALLOYS
ZIRCALOY