Numerical Simulation Research on Three-dimensional Temperature Field and Flow Field at the Top of Reactor under Natural Convection Conditions

Tang Xiangdong; Li Wei

doi:10.13832/j.jnpe.2023.S2.0044

Volume 44 Issue S2

Dec. 2023

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Tang Xiangdong, Li Wei. Numerical Simulation Research on Three-dimensional Temperature Field and Flow Field at the Top of Reactor under Natural Convection Conditions[J]. Nuclear Power Engineering, 2023, 44(S2): 44-49. doi: 10.13832/j.jnpe.2023.S2.0044

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Tang Xiangdong, Li Wei. Numerical Simulation Research on Three-dimensional Temperature Field and Flow Field at the Top of Reactor under Natural Convection Conditions[J]. Nuclear Power Engineering, 2023, 44(S2): 44-49. doi: 10.13832/j.jnpe.2023.S2.0044

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Numerical Simulation Research on Three-dimensional Temperature Field and Flow Field at the Top of Reactor under Natural Convection Conditions

doi: 10.13832/j.jnpe.2023.S2.0044

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

Received Date: 2023-07-11
Rev Recd Date: 2023-08-16
Publish Date: 2023-12-30

Abstract

Abstract

There are many equipment at the top of reactor in PWR, and the temperature and flow fields are complex. In order to evaluate the feasibility of cooling the control rod drive mechanism (CRDM) by natural convection, based on FLUENT software, the numerical simulation of the reactor top structure under natural convection conditions was carried out, and the flow field, temperature field distribution and the maximum coil temperature rise under four conditions were obtained. The simulation results show that under different operating conditions, the heat generated by CRDM operation can be completely taken out of the pit by natural convection, and there is no pit heat. The coil temperature of the CRDM will not exceed its operating temperature limit. This research can provide an important basis for cooling the CRDM using natural convection.
- PWR,
- CRDM,
- Temperature field,
- Natural convection

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References

[1]	郑海峰,钟艳敏,王源,等. 先进堆长寿命控制棒驱动机构热态寿命考验[J]. 核动力工程,2002, 23(S1): 70-73.
[2]	何培峰,许斌,罗英,等. ACP100集成式堆顶结构可压缩气体对流传热数值模拟[J]. 核技术,2016, 39(10): 100601.
[3]	何培峰,许斌,罗英,等. 基于HyperMesh的反应堆堆顶结构高质量计算流体力学网格生成[J]. 应用力学学报,2017, 34(2): 281-286.
[4]	于浩,张明,张伟,等. 反应堆流场分析的数值模拟[J]. 计算机辅助工程,2014, 23(6): 91-93.
[5]	张明,姚伟达,林绍萱,等. 核电厂反应堆部件及构筑物的三维流场数值模拟[C]//第五届中国CAE工程分析技术年会论文集. 兰州: 中国力学学会,中国机械工程学会机械工业自动化分会,中国力学学会促进工程应用与产业结合工作委员会,中国软件行业协会数学软件分会,陕西省国防科技工业信息化协会,2009: 684-691.
[6]	邹鹏,王建军,葛增芳,等. 控制棒驱动机构自然循环冷却方式的可行性研究[J]. 核技术,2014, 37(3): 030604.

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