Published 1996
| Version v1
Report
Restricted
Failures of the thermal barriers of 900 MWe reactor coolant pumps
Creators
Description
This report describes the anomalies encountered in the thermal barriers of the reactor coolant pumps in French 900 MWe PWR power stations. In addition to this specific problem, it demonstrates how the fortuitous discovery of a fault during a sampling test enabled faults of a generic nature to be revealed in components which were not subject to periodic inspection, the failure of which could seriously affect safety. This example demonstrates the risk which can be associated with the deterioration in areas which are not examined periodically and for which there are no preceding signs which would make early detection of deterioration possible
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 4th NRC/ASME symposium on valve and pump testing
- Imprint Pagination
- 719 p.
- Journal Page Range
- p. 1A.39-1A.50.
- Report number
- NUREG/CP--0152
Conference
- Title
- 4. NRC/ASME symposium on valve and pump testing in nuclear power plants.
- Dates
- 15-18 Jul 1996.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28014185
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; ELECTRIC MOTORS; FAILURES; FRANCE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; THERMAL BARRIERS; WATER PUMPS
- Descriptors DEC
- COOLING SYSTEMS; DEVELOPED COUNTRIES; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; EUROPE; MOTORS; POWER REACTORS; PUMPS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Secondary number(s)
- CONF-9607103--.