SOME EXPERIMENTS ON HIGH TEMPERATURE AQUEOUS CORROSION OF METALLIC URANIUM FUEL ELEMENTS WITH DEFECTED CLADDING.
Journal Article
·
· J. Nucl. Mater., 27: 264-74(Sept. 1968).
- Research Organization:
- CISE, Milan
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-22-049690
- OSTI ID:
- 4480240
- Report Number(s):
- CISE-E-675
- Journal Information:
- J. Nucl. Mater., 27: 264-74(Sept. 1968)., Other Information: Orig. Receipt Date: 31-DEC-68
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
N30110* -Metals
Ceramics
& Other Materials-Metals & Alloys-Corrosion & Erosion & Surface Phenomena
COOLANT LOOPS
CORROSION
DEFECTS
FUEL CANS
FUEL ELEMENTS
HEATING
HIGH TEMPERATURE
MATERIALS TESTING
METALLOGRAPHY
REACTION KINETICS
STEAM
THERMODYNAMICS
URANIUM
WATER
ZIRCALOY
STEAM/corrosive effects at high temperatures on defected Zircaloy-2-clad uranium fuels
REACTOR FUEL ELEMENTS/corrosion of Zircaloy-2-clad uranium
by high temperature steam-water mixtures
URANIUM/ corrosion of defected Zircaloy-2-clad
by high-temperature steam-water mixtures
ZIRCALOY-2/corrosion of extruded fuel element cladding of
by high-temperature steam-water mixtures
Ceramics
& Other Materials-Metals & Alloys-Corrosion & Erosion & Surface Phenomena
COOLANT LOOPS
CORROSION
DEFECTS
FUEL CANS
FUEL ELEMENTS
HEATING
HIGH TEMPERATURE
MATERIALS TESTING
METALLOGRAPHY
REACTION KINETICS
STEAM
THERMODYNAMICS
URANIUM
WATER
ZIRCALOY
STEAM/corrosive effects at high temperatures on defected Zircaloy-2-clad uranium fuels
REACTOR FUEL ELEMENTS/corrosion of Zircaloy-2-clad uranium
by high temperature steam-water mixtures
URANIUM/ corrosion of defected Zircaloy-2-clad
by high-temperature steam-water mixtures
ZIRCALOY-2/corrosion of extruded fuel element cladding of
by high-temperature steam-water mixtures