Published 1985
| Version v1
Book
Analysis of BWR core nuclear thermal hydraulic oscillation with three dimensional transient program
Creators
- 1. Hitachi Ltd., Hitachi, Ibaraki
Description
A three-dimensional BWR core dynamics program STANDY has been developed. STANDY takes into account parallel channel effect and evaluates fuel thermal margin. Peach Bottom 2 and Vermont Yankee stability test data have been analyzed by STANDY. Calculated decay ratios and resonance frequencies agreed well with measured data. Limit cycle oscillation at Vermont Yankee test has been also simulated. Oscillation amplitude agreed well with experiment. A hypothetical core condition has been made up to examine unstable oscillation in BWR core. Analyses of the core revealed that oscillation at conditions close to instability initiation reaches small amplitude limit cycle, and change in fuel thermal margin is very small during the limit cycle
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-122-3
- Imprint Title
- Proceedings of third international topical meeting on reactor thermal hydraulics
- Journal Page Range
- p. 9.D1-9.D7.
Conference
- Title
- 3. international meeting on reactor thermal hydraulics.
- Dates
- 15-18 Oct 1985.
- Place
- Newport, RI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065847
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMPLITUDES; COMPUTER CALCULATIONS; DATA PROCESSING; FUEL CHANNELS; HYDRAULICS; OSCILLATIONS; PEACH BOTTOM-2 REACTOR; POWER DISTRIBUTION; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; S CODES; THERMODYNAMICS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; TURBULENT FLOW; VERMONT YANKEE REACTOR
- Descriptors DEC
- BWR TYPE REACTORS; COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS