NUCLEAR FUELS NEWSLETTER
Data are given from studies of: density, hardness, and thermal expansion of Th-- Pu alloys: phase diagrams of U--Ru, U--Mo, and U--Ru--Mo: corrosion of U-- Ru in distilled water at 100 deg C: transformation kinetics of U--Nb--Zr U--Nb-- Ti, and U--Nb--V: radiation effects on U--Mo SRE fuels; enthalpy and heat capacities of USi/sub 2/ and USi/sub 3/; reaction rates for uranium silicides and O/sub 2/ and N/sub 2/ gases: bend testing and swelling of powder metallurgy U-- Mg; effects of radiation and post-irradiation annealing on room-temperature tensile properties of U; swage-annealing of U--Th; radiation effects on U--Cr; structure of delta-phase U--Zr: volume increase in irradiation of U-- Zr; diffusion treatment of cladding defects in Zircaloy-2-clad U--Zr: suppression of UAl/sub 4/ formation in U--Al by 3 wt.% ternary additions of other materials; conversion of U/sub 3/O/sub 6/ to UO/sub 2/ in composite Al fuel plates after heat treatment to 600 deg C; compatibility of aluminum and uranium carbides in compacts: and physical properties of gamma phase U--Nb--Zr. (T.R.H.)
- Research Organization:
- Division of Research, AEC
- NSA Number:
- NSA-14-015027
- OSTI ID:
- 4186550
- Report Number(s):
- WASH-703
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM-- CARBIDES-- COMPACTS-- URANIUM COMPOUNDS
ALUMINUM-- CONVERSION-- FUELS-- HEAT TREATMENTS-- OXIDES-- PLATES-- URANIUM COMPOUNDS-- URANIUM DIOXIDE-- URANIUM OXIDES
ANNEALING-- IRRADIATION-- RADIATION EFFECTS-- TENSILE PROPERTIES-- URANIUM
ANNEALING-- THORIUM ALLOYS-- URANIUM ALLOYS
BOILING-- CORROSION-- DISTILLATION-- RUTHENIUM ALLOYS-- URANIUM ALLOYS-- WATER
CANNING-- DEFECTS-- DIFFUSION-- FUEL CANS-- URANIUM ALLOYS-- ZIRCALOY-- ZIRCONIUM ALLOYS
CHEMICAL REACTIONS-- NITROGEN-- OXYGEN-- REACTION KINETICS-- REACTION RATE-- URANIUM SILICIDES
CHRO
METALS, CERAMICS, AND OTHER MATERIALS