Abstract
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 analyses, 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.
| Original language | English |
|---|---|
| Pages (from-to) | 625-633 |
| Number of pages | 9 |
| Journal | Journal of Nuclear Science and Technology |
| Volume | 45 |
| Issue number | 7 |
| DOIs | |
| Publication status | Published - 2008 Jan 1 |
| Externally published | Yes |
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Keywords
- CFD
- Complex flow field
- Elementary phenomenon
- Error estimation
- Feed water sparger
- Hydraulic gradient
- Numerical analysis error
- Opposed jet
- Sensitivity analysis
- Separator
- Tube banks
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
Cite this
Error estimation of values obtained from practical CFD analysis. / Uchida, Ken; Kawamura, Shinichiro.
In: Journal of Nuclear Science and Technology, Vol. 45, No. 7, 01.01.2008, p. 625-633.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Error estimation of values obtained from practical CFD analysis
AU - Uchida, Ken
AU - Kawamura, Shinichiro
PY - 2008/1/1
Y1 - 2008/1/1
N2 - 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 analyses, 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.
AB - 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 analyses, 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.
KW - CFD
KW - Complex flow field
KW - Elementary phenomenon
KW - Error estimation
KW - Feed water sparger
KW - Hydraulic gradient
KW - Numerical analysis error
KW - Opposed jet
KW - Sensitivity analysis
KW - Separator
KW - Tube banks
UR - http://www.scopus.com/inward/record.url?scp=46749138307&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=46749138307&partnerID=8YFLogxK
U2 - 10.1080/18811248.2008.9711461
DO - 10.1080/18811248.2008.9711461
M3 - Article
AN - SCOPUS:46749138307
VL - 45
SP - 625
EP - 633
JO - Journal of Nuclear Science and Technology
JF - Journal of Nuclear Science and Technology
SN - 0022-3131
IS - 7
ER -