Source Journal for Chinese Scientific and Technical Papers
Core Journal of RCCSE
Included in JST China
Included in the Hierarchical Directory of High-quality Technical Journals in Architecture Science Field
Volume 51 Issue 12
May  2022
Turn off MathJax
Article Contents
LIU Kai, LIU Jiaxing, XU Haixiang, YANG Xinguang, WANG Zhe. COMPARISONS OF TECHNICAL STANDARDS AT HOME AND ABOARD FOR STRUCTURAL INTEGRITY TESTS OF PRESTRESSED CONCRETE CONTAINMENTS[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 64-67,78. doi: 10.13204/j.gyjzg21102026
Citation: LIU Kai, LIU Jiaxing, XU Haixiang, YANG Xinguang, WANG Zhe. COMPARISONS OF TECHNICAL STANDARDS AT HOME AND ABOARD FOR STRUCTURAL INTEGRITY TESTS OF PRESTRESSED CONCRETE CONTAINMENTS[J]. INDUSTRIAL CONSTRUCTION, 2021, 51(12): 64-67,78. doi: 10.13204/j.gyjzg21102026

COMPARISONS OF TECHNICAL STANDARDS AT HOME AND ABOARD FOR STRUCTURAL INTEGRITY TESTS OF PRESTRESSED CONCRETE CONTAINMENTS

doi: 10.13204/j.gyjzg21102026
  • Received Date: 2021-10-20
    Available Online: 2022-05-27
  • Combined with the technical requirement of standards at home and aborad on structural strength tests for prestressed concrete containments, the test cycle, the process and the acceptance criteria were compared, the differences of standards were pointed out. Combined with a structural strength test of raising pressure and descending pressure in a practical project, some suggestions on the strength test in the structural integrity test of containments were proposed, which would provide reference to the successful implementation of the subsequent of structure strength test for containments in China.
  • loading
  • [1]
    李小将, 梁招瑞, 张心斌, 等.核电站安全壳钢衬里作用探讨[J].工业建筑, 2012, 42(增刊1):179-182.
    [2]
    中华人民共和国国家核安全局.核动力厂设计安全规定:HAF102-2004[S].北京:中华人民共和国国家核安全局, 2004.
    [3]
    柳胜华, 葛鸿辉, 张瑞, 等.不同国家对核电厂安全壳结构完整性试验要求综述分析[J].核标准计量与质量, 2017, 3(7):34-39.
    [4]
    中华人民共和国国家能源局.核电厂预应力混凝土安全壳结构在役检查要求:NB/T 20505-2018[S].北京:中国原子能出版社, 2018.
    [5]
    中华人民共和国国家能源局.压水堆核电厂预应力混凝土安全壳设计规范:NB/T 20303-2014[S].北京:新华出版社, 2014.
    [6]
    US Nuclear Regulatory Commission.Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures with Grouted Tendons:Regulatory Guide 1.90[S].Washington DC:US Nuclear Regulatory Commission, 1997.
    [7]
    法国核岛设备设计、建造及在役检查规则协会, 中科华核电技术研究院有限公司.M310堆型(1000 MWe压水堆)核电厂土建设计与建造规则:RCC-C-1986[G]//法国核电厂设计和建造规则.上海:上海科学技术文献出版社, 2012.
    [8]
    法国核岛设备设计、建造及在役检查规则协会, 中科华核电技术研究院有限公司.压水堆核电厂土建设计与建造规则:RCC-1-1988[G]//法国核电厂设计和建造规则.上海:上海科学技术文献出版社, 2012.
    [9]
    中华人民共和国国家能源局.压水堆核电厂安全壳结构整体性试验:NB/T 20017-2010[S].北京:中国原子能出版社, 2010.
    [10]
    中华人民共和国国家能源局.压水堆核电厂预应力混凝土安全壳结构整体性试验:NB/T 20017-2021[S].北京:中国原子能出版社, 2021.
    [11]
    American Society of Mechanical Engineers (ASME).BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 2:Code for Concrete Containments[S].New York:ASME, 2007.
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Article Metrics

    Article views (137) PDF downloads(6) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return