Wear measurements of nuclear power plant components. Final report
The objective of this study is to measure the amount of cobalt released to the primary coolant by wear of components in the primary circuit of nuclear power plants. Since detailed measurement data prior to wear were not available for field components, the measurements were made relative to nearby unworn reference surfaces. In most cases a profilometer was used to ascertain the worn profiles. Wear of components that were too large to be moved or that were contaminated was measured by preparing plastic replicas of the worn regions for subsequent profilometer measurements. Measurements were performed on the following components: (1) two PWR control element drive mechanisms; (2) a PWR main coolant pump shaft; (3) eight PWR gate valve discs; (4) two PWR horizontal swing check valve bushings; (5) four BWR feedwater regulator valves; (6) a BWR feedwater swing check valve; and (7) two BWR two-stage pilot relief valves. Pre- and post-test weight change measurements also were used to determine the wear of the two control element drive mechanisms. The wear measurements showed that the cobalt release rate varied from 0.02 to 84 grams of cobalt per year.
- Research Organization:
- Battelle Columbus Labs., OH (USA); Combustion Engineering, Inc., Windsor, CT (USA)
- OSTI ID:
- 6816931
- Report Number(s):
- EPRI-NP-3444; ON: TI84920411
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
ACTIVITY LEVELS
PWR TYPE REACTORS
WEAR
COBALT ISOTOPES
COOLING SYSTEMS
ENERGY SYSTEMS
ISOTOPES
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