Marginal Research on IVR Capability of Alumina Nanofluid Enhanced Spherical Lower Head

Song Jian; Yu Hongxing; Deng Jian; Xiang Qing'an; He Xiaoqiang

doi:10.13832/j.jnpe.2022.01.0156

Volume 43 Issue 1

Feb. 2022

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Song Jian, Yu Hongxing, Deng Jian, Xiang Qing'an, He Xiaoqiang. Marginal Research on IVR Capability of Alumina Nanofluid Enhanced Spherical Lower Head[J]. Nuclear Power Engineering, 2022, 43(1): 156-162. doi: 10.13832/j.jnpe.2022.01.0156

Citation:

Song Jian, Yu Hongxing, Deng Jian, Xiang Qing'an, He Xiaoqiang. Marginal Research on IVR Capability of Alumina Nanofluid Enhanced Spherical Lower Head[J]. Nuclear Power Engineering, 2022, 43(1): 156-162. doi: 10.13832/j.jnpe.2022.01.0156

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Marginal Research on IVR Capability of Alumina Nanofluid Enhanced Spherical Lower Head

doi: 10.13832/j.jnpe.2022.01.0156

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2020-12-22
Rev Recd Date: 2021-04-28
Publish Date: 2022-02-01

Abstract

Abstract

In order to evaluate the extent to which alumina nanofluids can extend the IVR capability of the spherical lower head relative to pure water working medium, in this paper, the critical heat flux (CHF) mechanism model of alumina nanofluid based on bubble force balance and the wall heat flux partitioning CHF model are used to calculate the CHF of nanofluid on the outer surface of spherical lower head. The decay heat distribution sampling calculation is carried out by using the IVR analysis software CISER, and the random distribution of CHF on the wall of the lower head with the inclination angle is obtained. Compared with the theoretical value of the nanofluid CHF model, the influence of nanofluid on the marginal expansion of IVR capability is studied and judged by taking the CHF ratio less than 1 as the IVR success criterion. The results show that if no optimization measures are taken for the internal and external heat transfer composition of the lower head and only nanofluid is used to replace pure water working medium, the IVR capability margin of PWR nuclear power plant can be expanded to 1300 MW rated power level.
- Bubble force balance,
- Heat flux partitioning,
- Critical heat flux (CHF),
- In-vessel retention (IVR),
- Capability margin

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References(8)

References

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