Assessment of corrosion and fatigue damage to light water reactor metal containments
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (United States)
Description
This paper presents a generic procedure for estimating aging damage, evaluating structural integrity, and identifying mitigation activities for safe operation of boiling water reactor (BWR) Mark I metal containments and ice-condenser type pressurized water reactor (PWR) cylindrical metal containments. The mechanisms of concern that can cause aging damage to these two types of containments are corrosion and fatigue. Assessment of fatigue damage to bellows is also described. Assessment of corrosion and fatigue damage described in this paper include: containment design features that are relevant to aging assessment, several corrosion and fatigue mechanisms, inspection of corrosion and fatigue damage, and mitigation of damage caused by these mechanisms. In addition, synergistic interaction between corrosion and fatigue is considered. Possible actions for mitigating aging include enhanced inspection methods, maintenance activities based on operating experience, and supplementary surveillance programs. Field experience related to aging of metal containments is reviewed. Finally, conclusions and recommendations are presented
Additional details
Publishing Information
- Imprint Title
- Eighteenth water reactor safety information meeting. Volume 3, Pressure vessel integrity; Piping and NDE; Aging and components: Proceedings
- Imprint Pagination
- 574 p.
- Journal Page Range
- p. 271-296.
- Report number
- NUREG/CP--0114-Vol.3
Conference
- Title
- 18. water reactor safety information meeting.
- Dates
- 22-24 Oct 1990.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CORROSION; ICE CONDENSERS; INSPECTION; MECHANICAL STRUCTURES; MITIGATION; MONITORING; PWR TYPE REACTORS; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR SAFETY; RESEARCH PROGRAMS; US NRC
- Descriptors DEC
- CHEMICAL REACTIONS; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MAINTENANCE; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTORS; SAFETY; STEAM CONDENSERS; THERMAL REACTORS; US ORGANIZATIONS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-9010185--Vol.3.