Integrated flow and heat removal performance evaluation for cooling water systems in operating nuclear power generating stations
- 1. Bechtel Corp., San Francisco, CA (United States)
- 2. Portland General Electric Co., OR (United States)
Description
In nuclear power plant safety-related cooling systems, such as the Component Cooling Water System, performance must be closely monitored and characterized in order to ensure that the plant's ability to safely shut down during a Design Basis Accident is not compromised, and other operating requirements are met. This paper describes an integrated flow and heat removal performance analysis approach which greatly simplifies the task of evaluating system performance, when degraded by fouling and/or modified by design changes, thereby allowing improvement in performance and availability. Using this performance model it was also possible to refine plant administrative procedures for operating the plant during maintenance of the system as well as gaining a better understanding of the various modes of operation of the system
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. 139-144.
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
- 23067739
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLING; DESIGN; FOULING; INTEGRATED COOLING SYSTEMS; MODIFICATIONS; MONITORING; NUCLEAR POWER PLANTS; PERFORMANCE; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; WATER
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; REACTOR COMPONENTS; REMOVAL; SAFETY; SHUTDOWN; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-9009110--.