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Title: POWER REACTOR PROGRAM. PROGRESS REPORT TO E.I. du PONT de NEMOURS & COMPANY FOR THE PERIOD SEPTEMBER 1, 1960 THROUGH SEPTEMBER 30, 1960

Technical Report ·
OSTI ID:4080401

One tube of the demonstration set of outer tubes was extruded. Two prototype inner tubes were prepared for heattreatment. Simple bend tests indicated that the diffusion zone formed by heat-treatment of Zircaloy-clad U-1.5 wt.% Mo tubes is less detrimental to ductility than that formed by the diffusion heat-treatment of U-2 wt.% Zr. A prototype unalloyed uranium Vallecitos Boiling Water Reactor tube, designed for a shorter taper, had thin cladding at the front inner surface. The first U- 1 wt.% Si extrusion for capsule irradiation specimens deviated from the required dimensions because the cladding broke through the copper jacket and picked up on the die. Fabrication of dingot uranium specimens for capsule irradiation is proceeding. Three stainless-steel- Zircaloy joints were evaluated. (For preceding period see NMI-7231.) (W.L.H.)

Research Organization:
Nuclear Metals, Inc., Concord, Mass.
DOE Contract Number:
AT(30-1)-1565
NSA Number:
NSA-15-012582
OSTI ID:
4080401
Report Number(s):
NMI-7232
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English