Tube and shell side coupled thermal analysis of an HTGR helical tube once through steam generator using porous media method

被引:20
作者
Olson, Joshua Tanner [1 ]
Li, Xiaowei [1 ]
Wu, Xinxin [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China
基金
中国国家自然科学基金;
关键词
High temperature gas-cooled reactor; Helical tube; Once through steam generator; Porous media method; HEAT-TRANSFER; 2-PHASE FLOW; PLANT;
D O I
10.1016/j.anucene.2013.09.036
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
To ensure the safety and efficiency of high temperature gas-cooled reactors, it is critical to understand the temperature non-uniformity of their once through steam generators. Large temperature non-uniformity can cause overheating of the tubes and may require a reduction in output. In order to correctly predict the thermal distribution in the tube bundles of the steam generators, the effect of thermal mixing and coupled heat transfer between the primary and secondary sides should be considered. A two-dimensional computer code based on the porous media method, coupling the tube and shell side of the steam generator was developed. This code was used to predict the thermal performance of the once through steam generator under normal operating conditions. The temperature non-uniformities caused by geometric and thermal-hydraulic deviations were also analyzed. It was found that a 1% change in the flow rate for a given tube line resulted in a temperature variation of 5 degrees C while shifting a tube line by I mm caused a temperature variance of 7 degrees C. It was also found that a plugged tube caused a large increase in temperature for the remaining tubes in the tube line. Finally, the influence of Peclet number on temperature was analyzed. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码:67 / 77
页数:11
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