Error estimation of values obtained from practical CFD analysis
Creators
- 1. Toshiba Corporation, Power and Industrial Systems R and D Center, Yokohama, Kanagawa (Japan)
- 2. Toshiba Corporation, Isogo Nuclear Engineering Center, Yokohama, Kanagawa (JP)
Description
In recent years, it has become common to analyze the detailed, three-dimensional flow features in reactor pressure vessels of boiling water reactors (BWRs) by computational fluid dynamics (CFD) analysis. However, there are few reports on practical examples of estimation or on estimation methodologies of the uncertainties in multi-dimensional CFD analysis. In this paper, to estimate the errors of values obtained from practical CFD analysis of a complex flow field, we propose a quantitative methodology that adopts the numerical analysis errors of 'elementary phenomena' as error factors for sensitivity analysis, as well as, for instance, dimensional tolerances or errors of input values. Using this methodology with CSAU methodology, we showed a practical simplified example of error estimation regarding calculated water surface drop along the radial direction obtained from CFD analysis of the hydraulic gradient formed in the reactor pressure vessel of a BWR. We show the validity of the methodology by comparing this 'estimated error' with a 'reference error' evaluated by comparing numerical and experimental results. (author)
Additional details
Identifiers
- DOI
- 10.3327/jnst.45.625;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 45
- Journal Issue
- 7
- Journal Page Range
- p. 625-633
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39106811
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; ERRORS; FEEDWATER; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; JETS; NUMERICAL ANALYSIS; PRESSURE DROP; PRESSURE VESSELS; SAFETY MARGINS; SENSITIVITY ANALYSIS; SPARGERS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDROGEN COMPOUNDS; MATHEMATICS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available from doi: http://dx.doi.org/10.3327/jnst.45.625; 7 refs., 12 figs., 1 tab.