Lessons learned from fatique failures in major FWR components
Description
This paper evaluates the field fatigue failure experience and describes the lessons learned that can be employed in managing fatigue damage at the sites of these failures and at other susceptible sites. Fatigue damage has resulted in cracks on the inside surfaces of vessels and piping, and in some cases, through-wall cracks resulting in coolant leakage. All of the fatigue failures resulted from conditions or stressors that were not accounted for in the original design analyses. In some cases, it has proven difficult to discover fatigue cracks using conventional inservice inspection methods; several cracks were detected because of leakage. Supplementary monitoring and inspection techniques such as fatigue monitoring, acoustic emission monitoring, and time-of-flight-diffraction ultrasonic testing can be used to assist in identifying susceptible sites, estimating crack growth, and sizing existing fatigue cracks. It is important to identify the root cause of failures because once the stressors and degradation mechanisms are known, changes in operating procedures and designs can be implemented to mitigate future fatigue damage
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Aging Research Information Conference
- Imprint Pagination
- 556 p.
- Journal Page Range
- p. 275-295.
- Report number
- NUREG/CP--0122-Vol.1
Conference
- Title
- Aging research information conference.
- Dates
- 24-27 Mar 1992.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24050764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CORROSION; CRACK PROPAGATION; FAILURES; FATIGUE; FRACTURES; IN-SERVICE INSPECTION; MONITORING; PWR TYPE REACTORS; REACTOR COMPONENTS; WATER COOLED REACTORS
- Descriptors DEC
- CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; INSPECTION; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-920375--Vol.1.