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Primary-side deposits on PWR steam-generator tubes

Technical Report ·
OSTI ID:6455151
; ;
The evaluation of analyses of material removed from primary side steam generator tubing samples taken from nuclear plants that had operated for up to 7 effective full power years are presented in this report. The types of analyses incuded radiochemical, chemical, scanning electron microscope (SEM), and energy dispersive x-ray (EDAX) techniques to characterize the surfaces and composition of the tubing material. An evaluation of the data obtained and a comparison with in-core crud data and with values calculated by a mathematical activity transport model (CORA) are also given in the report.
Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA)
OSTI ID:
6455151
Report Number(s):
EPRI-NP-2968; ON: DE83901952
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTIVITY LEVELS
BOILERS
CHEMICAL COMPOSITION
CHEMICAL REACTIONS
CORROSION
CORROSION PRODUCTS
DEPOSITS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS