Development and Application of a New CHF Correlation for PWR Fuel Assembly

Liu Wei; Peng Shinian; Jiang Guangming; Liu Yu

doi:10.13832/j.jnpe.2019.01.0008

Volume 40 Issue 1

Feb. 2019

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Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu. Development and Application of a New CHF Correlation for PWR Fuel Assembly[J]. Nuclear Power Engineering, 2019, 40(1): 8-11. doi: 10.13832/j.jnpe.2019.01.0008

Citation:

Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu. Development and Application of a New CHF Correlation for PWR Fuel Assembly[J]. Nuclear Power Engineering, 2019, 40(1): 8-11. doi: 10.13832/j.jnpe.2019.01.0008

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Development and Application of a New CHF Correlation for PWR Fuel Assembly

doi: 10.13832/j.jnpe.2019.01.0008

Publish Date: 2019-02-15

Abstract

Abstract

Based on the bundle CHF test database of NPIC, the minimum DNBR point method is applied in this study to develop a new CHF correlation named CF-DRW correlation for the PWR fuel assembly to couple with the subchannel code CORTH. The results of typical accidents analysis indicate that the DNBR thermal margin of CF-DRW correlation is almost equivalent or even larger than the FC-2000 correlation.
- PWR,
- Fuel assembly,
- Critical Heat Flux (CHF) correlation,
- Sub-channel analysis