超临界水冷堆CSR1000燃料组件子通道分析

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Subchannel Analysis of SCWR CSR1000 Assembly

CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 利用实验数据和计算流体力学(CFD)商用软件CFX对现有子通道分析模型进行研究,分析其在超临界水冷堆(SCWR)分析中的适用性,并根据分析结果对ATHAS程序进行改进。采用改进的ATHAS程序对超临界水冷堆CSR1000燃料组件进行稳态子通道分析,获得燃料组件冷却剂和包壳温度分布、流动压降等参数。结果表明:减小螺旋肋螺距(H_w)可展平燃料组件冷却剂出口温度分布、降低包壳表面最高温度(MCST),但同时燃料组件流动阻力将增大。
- 超临界水冷堆 /
- 燃料组件 /
- 子通道分析
Abstract: Subchannel analysis models have been investigated for SCWR fuel assembly by using experimental data available and Computational Fluid Dynamics（CFD） code in the present paper,which applicability in SCWR analysis is also analyzed,and the analysis results is used to improve the ATHAS code.The steady state subchannel analysis is conducted on the CSR1000 fuel assembly using the improve ATHAS,to obtain the temperature distribution of coolant and cladding and pressure drop in assembly.The result shows that,smaller pitch will flatten the profile of coolant temperature and reduce MCST,but it also increases the pressure drop in the assembly.
- Supercritical water-cooled reactor /
- Assembly /
- Subchannel analysis