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基于漂移流模型的核电蒸汽发生器稳态热工水力分析程序

A thermal hydraulic code for steady analysis of nuclear steam generator based on the drift flux model

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【作者】 张小英陈焕栋陈佳跃黄凯

【Author】 ZHANG Xiao-ying;CHEN Huan-dong;CHEN Jia-yue;HUANG Kai;China Nuclear Power Technology Research Institute;School of Electric Power,South China University of Technology;

【机构】 中科华核电技术研究院华南理工大学电力学院

【摘要】 为研究U形管核电蒸汽发生器的稳态热工水力特性,基于四方程漂移流模型开发了一维分析程序。对蒸汽发生器U形管束空间考虑为一次侧通道、二次侧通道和传热管壁构成,对一次侧通道和二次侧通道的过冷段采用单相流模型,二次侧通道的沸腾段采用4方程漂移流模型,建立基于交错网格的一阶迎风差分方程,通过热平衡-自然循环压降的交叉迭代计算得到稳态热工水力参数。利用程序计算了秦山一期核电机组,100%、75%、50%、30%、15%负荷稳定运行工况下的热工水力特性,并与程序RELAP5计算的结果比较。

【Abstract】 To study the steady thermal hydraulic characteristics of the U-tube nuclear steam generator,a 1D simulation code based on the 4-equation drift model has been developed.The U tube channels are considered to consist of the primary channel,secondary channel and the tube wall.Flowing in sub-cooling part of the primary and secondary channels is simulated with single phase flow model,and the boiling part in secondary channels is simulated with 4-equation drift flux model.The firstordered upwind differencing equations have been derived based on the staggered grid.An intersected updating method of heat balance and driving force requirement for natural circulation has been implemented to get the solution.As the application of the developed code,the steady thermal hydraulic characteristics for steam generator of the Qinshan I NPP,in 100%,75%,50%,30%,15%power condition,have been computed and compared with simulated results of RELAP5.

【基金】 国家自然科学基金项目51176052;广东省科技攻关项目2009B010900020
  • 【会议录名称】 中国核科学技术进展报告(第三卷)——中国核学会2013年学术年会论文集第3册(核能动力分卷(下))
  • 【会议名称】中国核学会2013年学术年会
  • 【会议时间】2013-09-11
  • 【会议地点】中国黑龙江哈尔滨
  • 【分类号】TL353.13;TM623
  • 【主办单位】中国核学会
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