Sources of internal hydriding in unirradiated thoria-fueled Zircaloy rods (LWBR Development Program)
The low-temperature (less than or equal to 550/sup 0/C), low-pressure (less than or equal to 36 torr) hydrogen absorption characteristics of specific types of Zircaloy-4 internal cladding surfaces (pickled, machined and welded) were investigated. The highest hydrogen contents were found at the machined and abraded surfaces. Although the pickled surface film on Zircaloy-4 retarded hydrogen pickup, especially at lower temperatures (less than or equal to 400/sup 0/C) and very low hydrogen pressures (less than or equal to 3.5 torr), some hydrogen was absorbed through the film even under these conditions. More hydrogen penetrated the pickled surfaces at higher temperatures and pressures. The pickled surfaces absorbed the hydrogen uniformly and without localization even with some film imperfections present. Little hydriding occurred when etched and welded Zircaloy-4 surfaces were exposed to water vapor at corrosion temperatures.
- Research Organization:
- Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
- DOE Contract Number:
- EY-76-C-11-0014
- OSTI ID:
- 6272759
- Report Number(s):
- WAPD-TM-1272; TRN: 79-012854
- Country of Publication:
- United States
- Language:
- English
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FUEL CANS
HYDRIDATION
LWBR TYPE REACTORS
ZIRCALOY 4
FUEL RODS
PRESSURE DEPENDENCE
TEMPERATURE DEPENDENCE
THORIUM OXIDES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
CHEMICAL REACTIONS
FUEL ELEMENTS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
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THERMAL REACTORS
THORIUM COMPOUNDS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* - Power Reactors
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