Development and Assessment of Improved Spacer Grid Model in Rod Bundle Subchannel

被引：0

作者：

Liu W. ^{[1
]}

Liu Y. ^{[2
]}

Li J. ^{[1
]}

Peng S. ^{[1
]}

Jiang G. ^{[1
]}

Liu Y. ^{[2
]}

Du S. ^{[1
]}

Qiu Z. ^{[1
]}

Deng J. ^{[1
]}

机构：

[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

[2] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2020年 / 41卷 / 04期

关键词：

Fuel assemblies; Spacer grid model; Subchannel analysis; Turbulent mixing;

D O I：

10.13832/j.jnpe.2020.04.0197

中图分类号：

学科分类号：

摘要：

In order to improve the prediction accuracy of two-phase local parameters in the rod bundle subchannel, based on the distributed resistance method, an improved spacer grid model is established in this paper, with the appropriate expression of the friction forces and a detailed model of mixing vane. The Carlucci turbulent mixing model is used to calculate the turbulent mixing rate, and the blocking factor is introduced to consider the turbulent mixing effect caused by the spacer grid. Coupled with subchannel analysis code ATHAS, the improved spacer grid model is used to calculate and analyze the PWR subchannel and bundle tests(PSBT) data. The results indicate that the improved spacer grid model has higher accuracy in predicting the distribution of the void fraction and outlet temperature in rod bundle subchannel. It lays a foundation for the accurate calculation of local parameters and CHF prediction in the rod bundle subchannel. © 2020, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：197 / 202

页数：5

共 7 条

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[7]

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