Progress is reported on the following studies: development of materials for Hanford reactors, developments for Al-clad fuel elements, studies of Zr-U alloys, corrosion studies of Zr, reactor-materials development, physical metallurgy, corrosion problems associated with the recovery of spent reactor fuel elements, evaluation of a reflector-controlled heterogeneous boiling reactor, studies of Na-Ta compatibility at elevated temperatures, and de velopment studies for the PWR. (For preceding period see BMI-1189.) (W.L.H.
Thermal-conductivity measurements were completed from 100 to 600 deg C on UO/sub 2/ specimens. An in...
Thermal-conductivity measuremerts of unirradiated U0/sub 2/ were started. The creep and rupture stre...
Items of significant technical progress which occurred in specific reactor projects and in general e...
Research is reported in the development of materials for Hanford reactors, development of Al-clad fu...
These three reports were issued separately, but are cataloged as a unit. Progress is reported in the...
Research is reported in the development of materials for Hanford reactors, development, of Al-clad f...
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...
>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...
Investigations are reported in: creep properties of annealed Zircaloy-2 and -3 at high temperatures;...
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...
Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. ...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
Thermal-conductivity measurements were completed from 100 to 600 deg C on UO/sub 2/ specimens. An in...
Thermal-conductivity measuremerts of unirradiated U0/sub 2/ were started. The creep and rupture stre...
Items of significant technical progress which occurred in specific reactor projects and in general e...
Research is reported in the development of materials for Hanford reactors, development of Al-clad fu...
These three reports were issued separately, but are cataloged as a unit. Progress is reported in the...
Research is reported in the development of materials for Hanford reactors, development, of Al-clad f...
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...
>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...
Investigations are reported in: creep properties of annealed Zircaloy-2 and -3 at high temperatures;...
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...
Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. ...
Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs...
Thermal-conductivity measurements were completed from 100 to 600 deg C on UO/sub 2/ specimens. An in...
Thermal-conductivity measuremerts of unirradiated U0/sub 2/ were started. The creep and rupture stre...
Items of significant technical progress which occurred in specific reactor projects and in general e...