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核电厂压力容器支座“流场-温度场”耦合分析 被引量:3

Analysis of coupling fluid-temperature-field for RPV
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摘要 反应堆压力容器(RPV)支座在核电厂设计中属ASME核安全1级支承,是关系到RPV安全的关键设备。通过建立支座的"流-固"耦合CFD模型和基于响应面法的实验设计,分析了支座入口空气流速和温度对支座温度场和空气流场的影响规律;进一步面向支座底面最高温度限制和减小空气流速的双目标要求,获得了优化的入口空气参数组合;最后通过对比"流-固"耦合模型结果和响应面法拟合结果,证明了模型和分析方法的正确性。 The support of reactor pressure vessel (RPV) is one of the most important equipment in nuclear power plant. The bottom temperature of support directly influences the temperature of its contacting concrete. By developing the "Fluid-Solid Coupling" CFD model and conducting experiment design using response surface method, the effects of velocity and tempera- ture of inlet air are investigated. Taking both temperature of support bottom and air highest velocity into consideration, the op- timal value of inlet air parameter was achieved.
出处 《机械研究与应用》 2012年第3期74-76,81,共4页 Mechanical Research & Application
关键词 压力容器支座 耦合分析 流场 温度场 响应面法 support of RPV coupling analysis flow field temperature ilield response surface method
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