考虑漏流的HTR-PM热气混合结构数值模拟研究
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摘要
对高温气冷堆核电厂示范工程HTR-PM的堆芯出口热气混合结构设计进行数值模拟,并考虑了未经过堆芯的冷却剂漏流的影响。对模拟计算所得的温度、压力以及流速分布的分析表明:热混合主要由与主流动方向垂直或平行的漩涡等二次流导致,且混合效果变化滞后于二次流的产生和变化;压降主要为由于流体流通面积和流动方向剧变而产生的局部压损,二次流的产生与变化伴随着压降的变化。计算分析的结果表明:在考虑漏流的额定流量工况下,HTR-PM的堆芯出口混合结构可以满足高热混合效率和低压降的要求。
The numerical simulation for the design of the hot gas mixing structure of Pebble-bed Module High Temperature gas-cooled Reactor(HTR-PM) are carried out with consideration of the leakage flow out of the reactor core. According to the profiles of temperature, pressure drop and flow velocity, the thermal mixing is mainly produced by the secondary flow such as the whirlpools which is perpendicular or parallel to the main flow direction. In addition, the pressure drop is mainly caused by the pressure loss leading by the sudden change of flow area and direction which is also the main reason of production of secondary flow. The numerical simulation indicates that the design of the hot gas mixing structure at HTR-PM reactor outlet can fulfill the requirement of high thermal mixing performance and low pressure drop by taking into account the leakage flow out of reactor with the condition of rated flow.
The numerical simulation for the design of the hot gas mixing structure of Pebble-bed Module High Temperature gas-cooled Reactor(HTR-PM) are carried out with consideration of the leakage flow out of the reactor core. According to the profiles of temperature, pressure drop and flow velocity, the thermal mixing is mainly produced by the secondary flow such as the whirlpools which is perpendicular or parallel to the main flow direction. In addition, the pressure drop is mainly caused by the pressure loss leading by the sudden change of flow area and direction which is also the main reason of production of secondary flow. The numerical simulation indicates that the design of the hot gas mixing structure at HTR-PM reactor outlet can fulfill the requirement of high thermal mixing performance and low pressure drop by taking into account the leakage flow out of reactor with the condition of rated flow.
引文
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[7]Zhou Y,Li F,Hao P,et al.Thermal hydraulic analysis for Hot gas mixing structure of HTR-PM[J].Nuclear Engineering and Design,2014,271:510-514.
[8]孙俊,郑艳华,李富.高温气冷堆侧反射层纵向窄缝中的旁流言就[J].原子能科学技术,2013,47(7):1151-1154.
[2]Yoshiyuki I,Kazuhiko K,Yoshiaki M,et al.Thermalhydraulic characteristics of coolant in the core bottom structure of the High-Temperature engineering Test Reactor[J].Nuclear Technology,1992,99(1):90-103.
[3]黄志勇.10MW高温气冷实验堆热气联箱混合性能研究[D].北京:清华大学核能与新能源技术研究院,1995.
[4]黄志勇,姚梅生,马昌文,等.高温气冷试验堆堆芯出口热气联箱混合性能对比试验[J].核动力工程,1997,18(1):37-42.
[5]王金华,薄涵亮,姜胜耀,等.高温堆热气联箱内部流场分析[J].核动力工程,2006,27(S1):23-29.
[6]周杨平,李富,郝鹏飞,等.HTR-PM堆芯出口热气混合实验相似性分析[J].原子能科学技术,2011,45(10):1208-1214.
[7]Zhou Y,Li F,Hao P,et al.Thermal hydraulic analysis for Hot gas mixing structure of HTR-PM[J].Nuclear Engineering and Design,2014,271:510-514.
[8]孙俊,郑艳华,李富.高温气冷堆侧反射层纵向窄缝中的旁流言就[J].原子能科学技术,2013,47(7):1151-1154.