Huadian Technology ›› 2015, Vol. 37 ›› Issue (10): 69-71.

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Comparative researches on the heat transfer characteristics of the SG between AP1000 and 2rd generation nuclear power plant

  

  1. 1.Nuclear Safety and Thermal Power Standardization InstituteNorth China Electric Power UniversityBeijing 102206China2.Key Laboratory of Passive Technology of BeijingBeijing 102206China
  • Online:2015-10-25 Published:2016-01-13

Abstract:

Abstract:By calculating the thermal resistance of the primary loop,the secondaryloopthe tube wall,the fouling resistance,the heat transfer coefficient ofsteam generators for AP1000,the Daya Bay Nuclear Power Plant and Qinshan Nuclear Power Plantare calculatedand the results are analyzed by comparing with each other.The data shows thatthe heat transfer coefficient of the AP1000 steam generator is 8978W/(m2·℃), which is slightly larger than that of the Daya Bays and Qinshans.Meanwhilethe secondary loop of AP1000 SG has the minimum thermal resistance of the three,but the thermal resistance of the primary loop,fouling resistance and thermal resistance values of the wall tube are
basically equal to those of Daya Bay,and both are superior to the corresponding values of Qinshan.The heat resistance of the tube wall account for more than 50% of the general heat resistance.Overall,the designs of each part of AP1000 steam generator are more reasonable
compared to the second generation of the steam generatorwhich improves its heat transfer characteristics.

Key words: ">Keywords:">AP1000">;">steam generator">;">heat exchange coefficient">;">geat resistance