The thermal conductivity and electrical resistivity of U encapsulated in Zircaloy-2 with NaK as a heat transfer material were determined prior to irradiation. The short-time rupture strength of 15% cold-worked Zircaloy-2 at 290, 345, and 4OO C is reported. Tests to develop the right-angle method of extrusion cladding of U with Al were continued. Pressure bonding of Al to Niplated U by temperature and gas-pressure tecchniques has produced sound metallurgical bonds. A series of 17 alloy compositions was prepared for corrosion testing in an effort to develop a natural-uranium fuel alloy with improved corrosion resistance. A stsdy of the oxidation …
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The thermal conductivity and electrical resistivity of U encapsulated in Zircaloy-2 with NaK as a heat transfer material were determined prior to irradiation. The short-time rupture strength of 15% cold-worked Zircaloy-2 at 290, 345, and 4OO C is reported. Tests to develop the right-angle method of extrusion cladding of U with Al were continued. Pressure bonding of Al to Niplated U by temperature and gas-pressure tecchniques has produced sound metallurgical bonds. A series of 17 alloy compositions was prepared for corrosion testing in an effort to develop a natural-uranium fuel alloy with improved corrosion resistance. A stsdy of the oxidation of U0/sub 2/ was continued. The corrosion of stainless steel by chloride-contaminated nitric acid solutions is reported. Studies are reported on the solidification of unalloyed U ingots. A study of the reactions that may occur during the induction melting of U is reported. Specimens of enriched UN or UC dispersed in stainless steel and clad with stainless steel were investigated to determine tensile properties at elevated temperatures and resistance to irradiation damage. Electrical resistivity and tensile strength measurements were made on U0/sub 2/ stainless steel cermets at room temperatures. Work has continued on the investigation of hydrides of U-Zr alloys as fueled moderators. Investigations of the radiation stability of U-Zr alloys is presented. Corrosion data are reported on gamma- phase uranium alloys. The preparation of U-Nb alloys is described. Oxidation data on Nb and Nb alloys tested in dry air at 1000 and 12OO C are reported and discussed. Degassing experiments at 450 to 650 C were successfully performed on Nb-H/sub 2/, permitting calculation of diffusion coefficients. Diffusion coefficients for hydrogen in delta zirconium hydride are given. The use of Ti as a construction material continues to appear promising for both dissolver and the feed adjustment tank for the Darex process. Limited evidence indicates the Al additions may be more suitable than thorium additions for cortrolling corrosiveness of initial Thorex solutions. The effects of sodium exposure on the creep behavior of tantalum are reported. The high-temperatore mechanical properties and weldability of tantalum are presented. Pressurebonding stodies of plate-type U0/sub 2/ fuel elements continued. Casting tecchniques are presented for UC. Data are given on the effect of processing variables on bulk density of sintered U0/sub 2/ pellets. (For precediag period see BMI-1256.) (W.L.H.)
Physical Description
Medium: P; Size: Pages: 64
Notes
Decl. July 18, 1958. Orig. Receipt Date: 31-DEC-59
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Dayton, Russell W. & Tipton, Clyde R., Jr.Progress Relating to Civilian Applications During March 1958,
report,
April 1, 1958;
Columbus, Ohio.
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