Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit

Yin Yuan; Feng Simin; Pang Bo; Xi Yanyan; Zhang Yuxiang; Fu Xiangang

doi:10.13832/j.jnpe.2023.04.0072

Volume 44 Issue 4

Aug. 2023

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Yin Yuan, Feng Simin, Pang Bo, Xi Yanyan, Zhang Yuxiang, Fu Xiangang. Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit[J]. Nuclear Power Engineering, 2023, 44(4): 72-78. doi: 10.13832/j.jnpe.2023.04.0072

Citation:

Yin Yuan, Feng Simin, Pang Bo, Xi Yanyan, Zhang Yuxiang, Fu Xiangang. Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit[J]. Nuclear Power Engineering, 2023, 44(4): 72-78. doi: 10.13832/j.jnpe.2023.04.0072

Citation:

Yin Yuan, Feng Simin, Pang Bo, Xi Yanyan, Zhang Yuxiang, Fu Xiangang. Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit[J]. Nuclear Power Engineering, 2023, 44(4): 72-78. doi: 10.13832/j.jnpe.2023.04.0072

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Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit

doi: 10.13832/j.jnpe.2023.04.0072

Yin Yuan^{1, 2
,},
Feng Simin^{1, 2},
Pang Bo^{1, 2
,
,},
Xi Yanyan³,
Zhang Yuxiang³,
Fu Xiangang³

1.
Department of Nuclear Science and Technology, Shenzhen University (SZU), Shenzhen, Guangdong, 518060, China
2.
Institute of Nuclear Power Operation Safety Technology (INPOST), Affiliated to the National Energy R & D Center on Nuclear Power Operation and Life Management, Shenzhen, Guangdong, 518060, China
3.
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518116, China

Received Date: 2022-08-19
Rev Recd Date: 2022-09-02
Publish Date: 2023-08-15

Abstract

Abstract

At present, the empirical correlations of critical heat flux (CHF) of advanced PWR rod-bundles at home and abroad generally have the common problems of complex mathematical form, numerous independent variable coefficients and lack of physical significance. In this study, based on 485 rod-bundle CHF data points of 5×5 PWR rod-bundles selected from the rod bundle CHF database of American Electric Power Research Institute (EPRI), a new dimensionless CHF correlation is developed with stepwise regression analysis. Considering the cold wall effect and axial non-uniform heating effect of the guide tube, the average value of the ratio M/P between the measured CHF and the predicted CHF is 0.998, the root mean square error is 0.0546, and the standard deviation is 0.0546. Based on the grouping method, the limit of the 95/95 departure from nucleate boiling ratio (DNBR) of the correlation is determined to be 1.16.
- Stepwise regression,
- Rod-bundle CHF,
- Dimensionless correlation,
- DNBR

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References(17)

References

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