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大亚湾核电站凝汽器壳侧流场和传热特性的二维数值分析与改进

Two-Dimension Numerical Analysis and Improvement of the Fluid Flow and Heat Transfer Performances in Daya Bay Nuclear Power Station Condenser

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【作者】 宫爱成臧希年秦广义许晔

【Author】 GONG Ai-cheng~1,ZANG Xi-nian~1,QIN Guang-yi~2,XUYe~3 (1.Tsinghua University, Beijing 100084, China; 2.TC, Guangdong Nuclear Power Holding Co. LTD, Shenzhen 518124, China; 3.Dongfang Steam Turbine Works, Deyang 618000, China)

【机构】 清华大学广核技术中心东方汽轮机厂 北京100084北京100084深圳518124德阳618000

【摘要】 采用凝汽器壳侧流场与传热特性计算软件,对大亚湾核电站凝汽器管束排列方式进行了二维数值分析,表明其排管方式存在显著的缺陷。计算表明:在布管空间不变的条件下,采用德国Balcke-Dürr公司的管束排列方式,其传热性能有很大的改善。图14表1参3

【Abstract】 Daya bay nuclear power station condenser’s bundle arrangement is analyzed through two-dimension numerical calculation program of steam flow field and heat transfer in condenser. The result indicates that the present bundle arrangement has some salient disadvantages. The new type bundle arrangement of German Balcke-Dürr Company has also been analyzed in the same condition as the present bundle arrangement, it makes great improvement in many ways. Figs 14, table 1 and refs 3.

  • 【文献出处】 动力工程 ,Power Engineering , 编辑部邮箱 ,2004年04期
  • 【分类号】TK264.1
  • 【被引频次】12
  • 【下载频次】178
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