FAST REACTOR CERAMIC FUELS RESEARCH.

Technical Report · Sat Oct 31 04:00:00 EST 1970

OSTI ID:4741474

• Research Organization: Battelle-Northwest, Richland, Wash. Pacific Northwest Lab.
• NSA Number: NSA-24-012462
• OSTI ID: 4741474
• Report Number(s): BNWL--1223
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

CHEMICAL ANALYSIS-- FUELS-- MIXING-- PLUTONIUM OXIDES-- STOICHIOMETRY-- URANIUM DIOXIDE
COMPRESSION-- MELTING-- SURFACE TENSION-- THERMAL CONDUCTIVITY-- URANIUM DIOXIDE-- VISCOSITY
CREEP-- HIGH TEMPERATURE-- IRRADIATION-- PLUTONIUM OXIDES-- RADIATION EFFECTS-- REACTOR CORE-- STRESSES-- URANIUM DIOXIDE
DESIGN-- ELECTRON MICROSCOPY-- ELECTRONIC EQUIPMENT
ELECTRON MICROSCOPES/ design of improved scanning
for examination of fuel materials
N30230* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
N38700 --Reactor Components
Fuels & Accessories
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
creep of polycrystalline
effects of various loadings at 1475 to 1560$sup 0$C on
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
radiation effects on creep of
in-pile
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
stoichiometry of mixed fuels of
method for determining
URANIUM OXIDES UO$sub 2$/PuO$sub 2$-- UO$sub 2$
creep of polycrystalline
effects of various loadings at 1475 to 1560$sup 0$C on
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
radiation effects on creep of
in-pile
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
stoichiometry of mixed fuels of
method for determining
URANIUM OXIDES UO$sub 2$/properties of fused
at 2755--C
URANIUM OXIDES UO$sub 2$/thermal diffusivity at 25 to 2500--C