首页> 外国专利> METHOD AND SYSTEM FOR DIAGNOSTICS OF MAXIMUM LOAD-BEARING CAPACITY OF PRESTRESSED PROTECTIVE SHELL OF NUCLEAR POWER PLANT WITH STRANDS WITHOUT ADHESION TO CONCRETE OF SHELL

METHOD AND SYSTEM FOR DIAGNOSTICS OF MAXIMUM LOAD-BEARING CAPACITY OF PRESTRESSED PROTECTIVE SHELL OF NUCLEAR POWER PLANT WITH STRANDS WITHOUT ADHESION TO CONCRETE OF SHELL

机译:核电站预应力保护壳的最大承载能力诊断方法和系统,其股线与壳体混凝土的粘连

摘要

FIELD: ensuring the bearing capacity of reinforced concrete protective shells of nuclear power plants.;SUBSTANCE: invention relates to means of ensuring the bearing capacity of reinforced concrete protective shells of nuclear power plants (NPP). A finite-element model of the NPP protective shell is formed, the required initial load-bearing capacity of the NPP protective shell is determined, taking into account data on the real tracing of strands and the forces in them from prestressing obtained from the sensors of the monitoring system and jacks, as well as taking into account the specified physical and mechanical properties of the shell structures. The sensors provide data on changes in the stress-strain state of the protective shell of the NPP, tension forces in the reinforced ropes, taking into account stress relaxation and the possibility of their slipping in the channel-forming agents, creep of concrete and other factors. Based on the obtained data, using the formed finite element model, the maximum load-bearing capacity of the NPP protective shell is predicted when it is loaded with an internal pressure exceeding the design pressure; next, the sufficiency of the tension forces of the strands or the necessary amount of their tightening is determined, or the conclusion that it is necessary to replace the strands is made. ;EFFECT: technical result is the possibility of diagnostics with the required reliability of the maximum load-bearing capacity of the nuclear power plant with strands installed without adhesion to the shell concrete, when loaded with internal pressure exceeding the design pressure, and, as a result, improving the safety of the nuclear power plant.;3 cl, 4 dwg
机译:田野:确保核电厂钢筋混凝土保护壳承载力。;物质:发明涉及确保核电厂(NPP)钢筋混凝土保护壳承载力的装置。形成NPP保护壳的有限元模型,确定了NPP保护壳的所需初始承载能力,考虑到股线的真实追踪的数据和从传感器获得的预应力中的力监控系统和千斤顶,以及考虑壳结构的指定物理和机械性能。传感器提供关于NPP的保护壳的应力 - 应变状态的变化数据,张力绳索中的张力力,考虑到应力松弛和它们在沟道形成剂中滑动,混凝土蠕变的可能性因素。基于所获得的数据,采用所形成的有限元模型,预测NPP防护壳的最大承载能力,当装入超过设计压力的内部压力时预测;接下来,确定股线的张力或其紧固量的张力的充分,或者结论是必要的制造股线。 ;效果:技术结果是诊断核电站最大承载能力的可能性,核电站的最大承载能力与安装的股线没有与壳体混凝土的粘连,当加载内部压力超过设计压力时,以及作为一个结果,提高核电站的安全性。; 3 CL,4 DWG

著录项

相似文献

  • 专利
  • 外文文献
  • 中文文献
获取专利

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号