CP1000-Type Nuclear Power Plant Containmnt Anchorage Zone Optimization

CP1000-type nuclear power plant is the second generation of improvedmillion-kilowatt nuclear technology with independent intellectual property rights inChina.Its structure using double containment to ensure that the adiation can pass throughthe inner containment,can not be discharged outside of the outer containment.According tothe relevant requirements of,a nuclear power engineering,on the basis of domesticanchorage system to optimize the structure of the anchorage zone.In order to ensure thesecurity,reliability of the nuclear power plant containment prestressed anchoragezone.According to the OVM Machinery Co.,Ltd base in concrete anchorage zone of theexisting,further research and analysis anchored in concrete.The project according toanchorage in the domestic nuclear power plant containment structure dimensions andforce characteristics,proposed the potimization model,use the Finite Element ComparativeAnalysis of bearing capacity,and load transfer test so that mutual authentication,to productthe Anchorage ystem that can ensure the safety of the anchorage zone.In this paper,toexpand the idea from the following aspects:First,this article describes the classification of the anchorage zone,countries on theordinary plate anchor ande special plate anchorage formula for the local carrying capacityof the local anchorage zone;also described the stress distribution in the concrete under theanchor;give the present stage of checking for concrete anchor under the three stressconcentration.On specific domestic and international norms formula for concrete prone tocrack under anchorage.Secondly,introduce the material element of th ANSYS finite element software modelselection for nuclear anchorage of the finite element analysis;study the modeling ofreinforecd concrete;give some suggestions in the handling of nonlinear boundaryconditions,the contact friction;proposed anchor in concrete local analysis andoptimization of design ideas.Calculation the original anchor plate (OVM15R-37C)withoptimized anchor plate(OVM15R-37CP)finite element results,determine the size of eachregion of the anchor under the device using both anchor stress values,contrast between thetwo side surface peeling and splitting stress, the load-dispalcement relationship,initiallyestablished the optimized anchor plate has a more reasonable form of the anchor plate tocomplete the first part of the optimized design.Again,finite element can not really determine whether the optimized anchor plate safeand reliable,according to the international FIP1993recommended load transfer validationtest,contrast it with the results of the finite element calculation,to product the anchorage system that can requirements of the building of nuclear power.Both use the Chinsesnational standard GB50010-2010《Design of Concrete Structures》to calculation theanchorage zone of prestressed layout anchor strure toverify its reliability.After the completion of the project, could further promote domestic anchoragesystem products used in building nuclear power plants, and the overall level of China’snuclear anchorage system may be raised.