Published November 1994
| Version v1
Report
Leakage prediction in nuclear power plants using similarity formulae and genetic algorithms
Creators
- 1. Instrumentation and Control Division, Oak Ridge National Lab., TN (United States)
Description
Safety issues of nuclear power plants include an early detection and identification of transients. In order to properly assess a transient, it is important to predict its severity. We predict the severity of several transients in an nuclear power plant using similarity based formulae and genetic algorithms. (authors); 8 refs., 1 tab., 3 figs
Additional details
Publishing Information
- Imprint Title
- Transactions of the nuclear societies of Israel Joint meeting 1994
- Imprint Pagination
- 234 p.
- Journal Volume
- 18
- Series
- Transactions of the nuclear societies of Israel joint meeting 1994.
- Journal Page Range
- (Pt.II) p. 10-14.
- Report number
- INIS-mf--14471
Conference
- Title
- 1994 joint meeting of the nuclear societies of Israel.
- Dates
- 28-29 Nov 1994.
- Place
- Tel Aviv (Israel).
INIS
- Country of Publication
- Israel
- Country of Input or Organization
- Israel
- INIS RN
- 26026018
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; ANALYTICAL SOLUTION; COMPUTER CODES; COMPUTERIZED SIMULATION; FAILURE MODE ANALYSIS; FEEDWATER; LEAKS; MATHEMATICS; MATRICES; RELIABILITY; RUPTURES; SAN ONOFRE-1 REACTOR; STEAM; STEAM LINES; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FAILURES; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; PIPELINES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS