Steam Generator Strength Computation for Nuclear Electric Power Plants of a Low Power

V. Kravchenko, O. Lymarenko, Z. Xiaolong, Kiril Khromiy, Yehor Buchka
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Abstract

Today, the world oversees an explosive development of the nuclear power stations (NPS) of a low power. Most projects deal with pressurized water reactors and as a matter of fact with steam generators (SG). Ukraine has a well-developed engineering industry backbone that can be used for the production of the equipment required for the nuclear power plants of a low power. This scientific paper delves into the computations of the strength of elements used for the monotube steam generator with cylindrical coils that is the most presentable of all the projects in question in IAEA materials. Appropriate methods were developed to perform structural computations and steam generator strength computations. The mathematical model was developed that allows us to perform strength computations of the SG elements making use of the analytical method with reference to the Regulations and do simulations using the ANSYS software code. The specified elements include the body elements, in particular the cylindrical part, the flange, the bottom and the cover, including the heat carrier branch pipe and heat exchange tubes. The comparison of the data obtained by both methods showed their similarity and accordingly, the accuracy of the data that are indicative of the need for an increase in the wall thickness of the cylindrical part of the external branch pipe intended for the heat carrier. The body bottom strain for calculated dimensions exceeds the permissible value by 1.56 %. Since this value is 5 % lower than permissible values it is deemed that the strength condition is passed through. The simulation proved that the strength conditions are met for heat exchange tubes, for the body, the body cover, the body flange, the conical part of the external branch pipe intended for the heat carrier. Based on the analysis done, we would like to recommend performing strength computations using the normative method with the subsequent check out by the simulation using the computer code.
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小功率核电站蒸汽发生器强度计算
如今,低功率核电站(NPS)在世界范围内呈爆炸式发展。大多数项目处理的是压水堆,实际上是蒸汽发生器(SG)。乌克兰拥有发达的工程工业支柱,可以用于生产低功率核电站所需的设备。这篇科学论文深入研究了用于具有圆柱形线圈的单管蒸汽发生器的元件强度的计算,这是原子能机构材料中所有有关项目中最引人注目的。制定了相应的结构计算和蒸汽发生器强度计算方法。建立了数学模型,使我们能够利用参考规则的解析方法进行SG单元的强度计算,并使用ANSYS软件代码进行模拟。所述指定元件包括本体元件,特别是圆柱部分、法兰、底部和盖,包括热载体支管和热交换管。两种方法得到的数据的比较显示了它们的相似性,因此,数据的准确性表明需要增加用于热载体的外部分支管的圆柱形部分的壁厚。计算尺寸的体底应变超出允许值1.56%。由于该值比允许值低5%,因此认为强度条件已通过。仿真结果表明,换热管、换热管本体、换热管盖、换热管法兰、换热管外支管锥形部分均满足强度要求。根据所做的分析,我们建议采用规范方法进行强度计算,随后使用计算机代码进行模拟验算。
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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