Principal factor analysis of the reactor coolant pump system
Creators
- 1. Yankee Atomic Electric Co., Bolton, MA (United States)
- 2. Marx Social Sciences Research Inc., Cambridge, MA (United States)
Description
In today's nuclear power plant operating environment, set points are established for key plant parameters, such as temperature, pressure, or flow rate. When these set points are exceeded, it is common practice to scram the reactor, resulting in plant shutdown for those cases where extended maintenance and repair are necessary. Reducing excursions beyond these set points would save millions of dollars as a result of improved plant availability and improve plant safety as well. In a recently published case study, classical statistical process control techniques were implemented on actual plant data gathered in real time over a 121-day period for the reactor coolant pump (RCP) system. Analysis of the data showed the eventual plant trip could have been anticipated by at least 15 days by using statistical methods
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 276-278
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036666
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AVAILABILITY; BWR TYPE REACTORS; CALIBRATION; CORRELATIONS; FAILURES; FLOW RATE; FORECASTING; IMPLEMENTATION; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR KINETICS; REACTOR MAINTENANCE; REACTOR SAFETY; REGRESSION ANALYSIS; RELIABILITY; SCRAM; TEMPERATURE DEPENDENCE
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; KINETICS; MAINTENANCE; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; STATISTICS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910603--.