Published September 1992 | Version v1
Report

Lessons learned from fatique failures in major FWR components

  • 1. Idaho National Engineering Lab., Idaho Falls (United States)

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

Part of:
Proceedings of the Aging Research Information Conference

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.