Stratification and the operational aspects of nuclear-power plants
- 1. Stone and Webster Engineering Corp., Boston, MA (United States)
- 2. Virginia Power, Innsbrook, VA (United States)
Description
Operating experience indicates that thermal stratification is a significant event unaccounted for in original nuclear-power-plant designs. With the aging of nuclear plants, the long-term effects of thermal stratification on several piping systems have been exhibited in through-wall cracks, damaged supports, and thermal fatigue. This paper describes a comprehensive program developed and implemented at Virginia Power's North Anna and Surry pressurized water reactor power stations to address thermal stratification of the pressurizer surge line. Field inspections, temperature and displacement measurements synchronized with various plant events, and analytical evaluations indicate that stratification can be satisfactorily accounted for without undue restrictions on plant operations and with only minor hardware modifications to the pipe supports and pipe whip restraints. The fatigue evaluation rigorously considered measured stratification profiles, specified operating conditions, striping, and additive thermal stratification cycles
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0528-X
- Imprint Title
- Excellent and economic nuclear plant performance
- Imprint Pagination
- 175 p.
- Journal Page Range
- p. 119-126.
Conference
- Title
- Joint American Nuclear Society (ANS) Power Division topical meeting and the American Society of Mechanical Engineers (ASME) nuclear energy conference.
- Dates
- 16-20 Sep 1990.
- Place
- Newport, RI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23067913
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CRACKS; DESIGN; FIELD TESTS; NUCLEAR POWER PLANTS; OPERATION; PIPES; PRESSURIZERS; PWR TYPE REACTORS; STRATIFICATION; TEMPERATURE DEPENDENCE; THERMAL FATIGUE
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FATIGUE; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9009110--.