核电站安全壳混凝土结构长期预应力预测模型初步研究
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  • 英文篇名:Primary research on nuclear power station containment concrete structure long-term prestress forecasting model
  • 作者:廖开星 ; 李毅 ; 孔祥龙 ; 汤志杰 ; 遆文新
  • 英文作者:LIAO Kaixing;LI Yi;KONG Xianglong;TANG Zhijie;TI Wenxin;Department of Ageing Management,Suzhou Nuclear Power Research Institute;
  • 关键词:安全壳 ; 预应力 ; 长寿期运行
  • 英文关键词:containment;;pressing;;long term operation
  • 中文刊名:HLTF
  • 英文刊名:Concrete
  • 机构:苏州热工研究院有限公司寿命中心老化管理技术研究所;
  • 出版日期:2015-05-27
  • 出版单位:混凝土
  • 年:2015
  • 期:No.307
  • 基金:国家高技术研究发展计划(863计划)(2012AA050901)
  • 语种:中文;
  • 页:HLTF201505040
  • 页数:5
  • CN:05
  • ISSN:21-1259/TU
  • 分类号:148-152
摘要
基于ACI209R-92、CEB-FIP(1990)、GL2000收缩与徐变模型基础,充分考虑了混凝土的收缩、徐变和预应力钢筋松弛的耦合作用后推导出安全壳长期预应力预测的计算模型。通过计算分析,其中基于CEB-FIP(1990)模型的预测值与实测值更为接近。采用3 000 h内的预应力监测值修正模型后,该模型对长期预应力值的预测更为合理。该研究成果为核电站的长寿期运行提供了很好的技术支撑。
        It provided a formulas for calculating the pressing value of the containment,which was deduced on considering the influence of concrete dry shrinkage,creep and the relaxation of prestress strand coupling effect basing on ACI209R-92,the CEB-FIP( 1990),GL2000 shrinkage and creep model.Through calculation and analysis,the prestress value calculating based on CEB-FIP( 1990) model is more close to the measured values.The model corrected by using prestress strand monitoring value within 3 000 h,and the prestress value predicted of this model is more reasonable.The results are a good technical support for long term operation of the nuclear power plants.
引文
[1]Nrc information notice 99-10,revision 1:Degradation of prestressing tendon systems in prestressed concrete containments[Z].
    [2]ACI Committee 209.Prediction of creep,shrinkage and temperature effects in concrete strcutures[S].Manual of concrete practice,Part 1.American Concrete Institute,209R,1992:1-92.
    [3]Comite euro-international du beton.Ceb-fip model code[S],1990.
    [4]GARDNER N J,LOCKMAN M J.Design provisions for drying shrinkage and creep of normal-strength concrete[J].ACI M aterials Journal,2001,98(2):159-167.
    [5]泮忠元,王社良.大体积混凝土(核电站安全壳)预应力损失分析[J].水利与建筑工程学报,2009,7(1):3.
    [6]王勋文,潘家英.按龄期调整有效模量法中的老化系数x的取值问题[J].中国铁道科学,1996,17(3):9.

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