FAST-REACTOR CERAMIC FUELS RESEARCH.

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

OSTI ID:4161893

• Research Organization: Battelle-Northwest, Richland, Wash. Pacific Northwest Lab.
• NSA Number: NSA-24-034971
• OSTI ID: 4161893
• Report Number(s): BNWL--1349-1
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

COMPRESSION-- CREEP-- DENSITY-- FUELS-- HEATING-- HIGH TEMPERATURE-- MELTING-- PLUTONIUM OXIDES-- POWDERS-- PRESSURE-- REMOTE HANDLING-- THERMAL CONDUCTIVITY-- URANIUM DIOXIDE
COMPRESSION-- CREEP-- DENSITY-- MEASUREMENT-- PRESSURE-- URANIUM DIOXIDE
METALLURGICAL EQUIPMENT/design for determining properties of oxide fuels
N30250* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N38700 --Reactor Components
Fuels & Accessories
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$-- UO$sub 2$
radiation effects on creep of encapsulated specimens of
in-pile
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
density of hot-pressed powders of
effects of pressing temperature on
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
thermal conductivity of solid solutions of
at 100 to 1200--C
REACTOR FUELS/properties of molten
design of facility for determination of
URANIUM OXIDES UO$sub 2$/ PuO$sub 2$--UO$sub 2$
density of hot-pressed powders of
effects of pressing temperature on
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
radiation effects on creep of encapsulated specimens of
in-pile
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
thermal conductivity of solid solutions of
at 100 to 1200--C
URANIUM OXIDES UO$sub 2$/creep of dense specimens of
compressive