Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Jun Huang, Weiguo Zhang, Xueyuan Liang, Feifei Wu, Jing Xu, Shaolin Zhang, Wen Yang, Zhiyao Tang
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Abstract

NB/T 20012-2010 design requirements for concrete structures related to nuclear safety of PWR nuclear power plants is a standard issued by the National Energy Administration in 2010. It is the top-level standard and important standard for concrete structure design. Due to technological progress and changes in relevant reference standards, some of its contents can not meet the requirements at this stage, On the basis of referring to the latest relevant standards and specifications at home and abroad, the engineering experience in the structural design of nuclear safety related plants of nuclear power plants built and under construction in China was summarized, and the chief editor revised it. This paper mainly analyzes the revised contents, mainly including revising the minimum strength grade of concrete was changed to C30, HRB500, HPB300 steel bars were added, and HPB235, HRB335 steel bars were canceled; improving the safety of the axial compression members that configure the ordinary stirrups, modifying the formula for calculating the bearing capacity of the transverse shear (that is, out-of-plane shear), modifying the formula for calculating the punching bearing capacity (considering the effects of membrane force) ; defining the load effect combination used in the calculation of crack width, and the maximum crack width is calculated according to the relevant specifications of GB 50010; stipulating that short-term stiffness is taken in deflection calculation under normal operation and severe environment, normal operation and extreme environment and abnormal operation conditions; adding contents of structural analysis, basic provisions of mechanism components and beyond the scope of design basis;The Appendix B (informative) “Performance Index of Reinforcement and Concrete at High Temperature” was added;.
中国压水堆核电站核安全相关混凝土结构设计规范修订分析与研究
NB/T 2002 -2010《压水堆核电站核安全相关混凝土结构设计要求》是国家能源局于2010年发布的标准。它是混凝土结构设计的最高标准和重要标准。由于技术进步和相关参考标准的变化,其部分内容已不能满足现阶段的要求,在参考国内外最新相关标准规范的基础上,总结了国内已建和在建核电站核安全相关电站结构设计的工程经验,并由主编进行了修订。本文主要分析了修改内容,主要包括将混凝土最小强度等级修改为C30,增加HRB500、HPB300钢筋,取消HPB235、HRB335钢筋;提高配置普通马镫的轴压构件的安全性,修改横向剪切(即面外剪切)承载力计算公式,修改冲孔承载力计算公式(考虑膜力的影响);定义了裂缝宽度计算中采用的荷载效应组合,最大裂缝宽度按GB 50010的有关规范计算;规定在正常运行和恶劣环境、正常运行和极端环境和异常运行条件下挠度计算采用短期刚度;增加结构分析内容、机构部件基本规定及超出设计依据范围;增加附录B(资料性)《钢筋混凝土高温性能指标》;
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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