Research is reported in the development of materials for Hanford reactors, development, of Al-clad fuel elements. plant assistance to MCW, reactions between HiO and Zr alloys, general fuel element development, Zr --U alloy studies, corrosion of Zr, reactor materials development, physical metallurgy, development of PWR, and Na-- Ta compatibility at high temperatures. (T.R.H.
Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. ...
Measurements of thermal conductivity and electrical resistivity were continued on irradiated specime...
A study of the creep properties of 15% cold-worked and annealed Zircaloy- 2 sheet at 290, 345, and 4...
Research is reported in the development of materials for Hanford reactors, development of Al-clad fu...
Progress is reported on the following studies: development of materials for Hanford reactors, develo...
These three reports were issued separately, but are cataloged as a unit. Progress is reported in the...
>Progress is reported on reactor materials and components, studies of fuels, general fuel-element de...
Research and development are reported in the flelds of reactor materials and components, fuel studie...
Progress is reported for investigations of: reactor materials and components; development of fuel el...
Data are given on: creep propenties of 15% coldworked Zircaloy-2; the liquidus in Al-U; effect of ch...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
A comparison of the creep properties of l5% cold-worked Zircaloy-2 and of annealed Zircaloy-2 is bei...
>The creep and stress-rupture propenties of annealed and of 15% cold- worked Zircaloy-2 are being de...
Progress is reported in corrosion studies of stainless steels, Nb, Zr, Al- Fe-Mo, Mo, Ni alloys, and...
Tests of materials for use in liquid-metal and fused-salt systems were continued. Corrosion tests, p...
Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. ...
Measurements of thermal conductivity and electrical resistivity were continued on irradiated specime...
A study of the creep properties of 15% cold-worked and annealed Zircaloy- 2 sheet at 290, 345, and 4...
Research is reported in the development of materials for Hanford reactors, development of Al-clad fu...
Progress is reported on the following studies: development of materials for Hanford reactors, develo...
These three reports were issued separately, but are cataloged as a unit. Progress is reported in the...
>Progress is reported on reactor materials and components, studies of fuels, general fuel-element de...
Research and development are reported in the flelds of reactor materials and components, fuel studie...
Progress is reported for investigations of: reactor materials and components; development of fuel el...
Data are given on: creep propenties of 15% coldworked Zircaloy-2; the liquidus in Al-U; effect of ch...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
A comparison of the creep properties of l5% cold-worked Zircaloy-2 and of annealed Zircaloy-2 is bei...
>The creep and stress-rupture propenties of annealed and of 15% cold- worked Zircaloy-2 are being de...
Progress is reported in corrosion studies of stainless steels, Nb, Zr, Al- Fe-Mo, Mo, Ni alloys, and...
Tests of materials for use in liquid-metal and fused-salt systems were continued. Corrosion tests, p...
Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. ...
Measurements of thermal conductivity and electrical resistivity were continued on irradiated specime...
A study of the creep properties of 15% cold-worked and annealed Zircaloy- 2 sheet at 290, 345, and 4...
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