SAXTON PLUTONIUM PROGRAM. Semiannual Progress Report for the Period Ending December 31, 1969.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
- NSA Number:
- NSA-24-026777
- OSTI ID:
- 4152760
- Report Number(s):
- WCAP--3385-22
- Country of Publication:
- United States
- Language:
- English
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ACTIVATION
BURNUP
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FAST NEUTRONS
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FUELS
GAMMA RADIATION
HYDROGEN
IRRADIATION
MECHANICAL PROPERTIES
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N30250 -- Metals
Ceramics
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NEUTRONS
OPERATION
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(E/T)
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
radiation effects on burnup
microstructure
and
USES
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY-4/corrosion film formation on pressurized water reactor fuel element cladding of
(E)
ZIRCALOY-4/radiation effects on $gamma$ activity, hydrogen content, and mechanical properties of, in-pile, (E)
BURNUP
CORROSION
DETERMINATION
FAST NEUTRONS
FILMS
FUEL CANS
FUELS
GAMMA RADIATION
HYDROGEN
IRRADIATION
MECHANICAL PROPERTIES
METALLOGRAPHY
MICROSTRUCTURE
N30250 -- Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N38150* --Power Reactor Development--Fuels
NEUTRON FLUX
NEUTRONS
OPERATION
PERFORMANCE
PLUTONIUM OXIDES
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$, radiation effects on burnup, microstructure, and mechanical properties of pressurized water reactor fuels of, in-pile, (E)
PLUTONIUM/utilization in pressurized water reactor fuels
(E/T)
POWER REACTORS
PRESSURIZED WATER REACTORS
RADIATION EFFECTS
REACTIVITY
REACTOR CORE
REACTOR KINETICS
REACTORS
PRESSURIZED-WATER/fuel elements for
performance of Zircaloy-4 clad plutonium oxide (PuO$sub 2$)--uranium oxide (UO$sub 2$)
(E/T)
SAXTON
SAXTON POWER REACTOR/ operation of
Core III zero power physics testing during
SAXTON POWER REACTOR/fuel element cladding for
fast neutron flux exposure of Core II
(E)
SAXTON POWER REACTOR/fuel elements for
in-pile performance of Zircaloy clad plutonium oxide (PuO$sub 2$)--uranium oxide (UO$sub 2$)
(E/T)
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
radiation effects on burnup
microstructure
and
USES
WATER COOLED REACTORS
ZIRCALOY
ZIRCALOY-4/corrosion film formation on pressurized water reactor fuel element cladding of
(E)
ZIRCALOY-4/radiation effects on $gamma$ activity, hydrogen content, and mechanical properties of, in-pile, (E)