Nuclear-component wear measurements. Final report. [PWR; BWR]
The objective of this study was to develop and demonstrate techniques for measuring the quantities of cobalt released to the primary coolant by wear of high-cobalt alloys. Without detailed pre-wear measurements being available for existing components, the approach was to measure the amount of wear relative to nearby unworn reference surfaces by developing in situ measurement techniques. Making plastic replicas of the worn areas was found to be a suitable approach for subsequent measurement in the laboratory. Wear measurements by the replication approach were found to agree in laboratory tests with actual weight-loss measurements within five percent. Field measurements were performed on the following cobalt containing components: the journal portion of a PWR main coolant pump shaft; two BWR feedwater regulator valves; a BWR cleanup discharge isolation valve; two BWR main steam isolation valves (MSIV); and two BWR feedwater pump turbine steam control valves.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 7095895
- Report Number(s):
- EPRI-NP-2684; ON: DE83900611
- Country of Publication:
- United States
- Language:
- English
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Nuclear component wear measurements
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Related Subjects
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
PUMPS
VALVES
WEAR
PWR TYPE REACTORS
COBALT ALLOYS
REACTOR MATERIALS
ALLOYS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
EQUIPMENT
FLOW REGULATORS
MATERIALS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled