Managing the aging of BWR control rod drive systems
Description
This Phase I Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with BWR control rod drive mechanisms (CRDMs) and assesses the merits of various methods of open-quote managingclose quotes this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each U.S. BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of the Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to the control rod drive (CRD) system, and (4) personal information exchange with nuclear industry CRDM maintenance experts. The report documenting the findings of this research, NUREG-5699, will be published this year. Nearly 23% of the NPRDS CRD system component failure reports were attributed to the CRDM. The CRDM components most often requiring replacement due to aging are the Graphitar seals. The predominant causes of aging for these seals are mechanical wear and thermal embrittlement. More than 59% of the NPRDS CRD system failure reports were attributed to components that comprise the hydraulic control unit (HCU). The predominant HCU components experiencing the effects of service wear and aging are valve seals, discs, seats, stems, packing, and diaphragms
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Aging Research Information Conference
- Imprint Pagination
- 556 p.
- Journal Page Range
- p. 503-524.
- 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
- 24050701
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; CONTROL ROD DRIVES; CORROSION; EVALUATION; FATIGUE; REACTOR COMPONENTS; REACTOR VESSELS
- Descriptors DEC
- CHEMICAL REACTIONS; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Secondary number(s)
- CONF-920375--Vol.1.