Research of the Stress-Strain State for Steel Support Structures of Nuclear Power Plant Components under Seismic Loads

Q2 Energy
O. Shugaylo, S. Bilyk
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引用次数: 0

Abstract

Seismic resistance of equipment and piping of nuclear power plant units is determined, particularly, by seismic resistance of their steel support structures. A significant number of these structures are located in the reactor building of nuclear power plants and belong to seismic resistance categories I and II. Therefore, such support structures of nuclear power plant equipment and piping, in general, shall perform their functions under seismic hazards that correspond to the safe shutdown earthquake and design-basis earthquakes, respectively. Steel support structures of serial equipment (piping valves, electric and pneumatic drives of piping and pump valves, expansion tanks, etc.) are often designed “on site” in the limited conditions of their actual location. Therefore, it is necessary to design steel support structures of a number of equipment taking into account the fact that it can be connected, in particular, to existing piping with their actual routing. In connection with the above, the research of operation for such support structures under seismic loads is relevant. The article presents the research results for the spectrum of natural oscillation frequencies of the equipment support structure, and the stress-strain state of the considered structure under seismic loads is determined. At the same time, the parameters during normal operation and maximum design basis accident at the nuclear power plant power unit are considered. The calculated combination of loads, which simultaneously includes two episodic impacts (maximum design basis accident and an earthquake) is considered.
地震荷载作用下核电厂构件钢支撑结构应力-应变状态研究
核电站机组设备和管道的抗震性能主要取决于其钢支撑结构的抗震性能。这些结构中有相当一部分位于核电站的反应堆建筑中,属于抗震一类和二类。因此,核电站设备和管道的此类支撑结构一般应在与安全停堆地震和设计基础地震相对应的地震灾害下发挥作用。系列设备的钢支撑结构(管道阀、管道和泵阀的电动和气动驱动、膨胀罐等)往往是在其实际位置的有限条件下“现场”设计的。因此,有必要在设计一些设备的钢支撑结构时,考虑到它可以连接,特别是与现有管道的实际走线相连。因此,对此类支撑结构在地震荷载作用下的运行进行研究是有意义的。本文介绍了设备支撑结构固有振动频率谱的研究成果,确定了考虑结构在地震荷载作用下的应力-应变状态。同时考虑了核电站动力机组正常运行时的参数和最大设计基础事故。计算的荷载组合同时考虑了两种偶发影响(最大设计基础事故和地震)。
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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来源期刊
Nuclear and Radiation Safety
Nuclear and Radiation Safety Energy-Nuclear Energy and Engineering
CiteScore
0.80
自引率
0.00%
发文量
18
期刊介绍: General issues of nuclear energy use; nuclear energy (reactor theory and calculations, operation of nuclear power plants, NPP safety analysis (probabilistic safety analysis, deterministic safety analysis), research reactors, nuclear fuel and structural materials, fuel elements; neutron physics; general safety issues; decommissioning of nuclear facilities; long-term operation, spent fuel and radioactive waste management; radiation safety; I&C, physical protection.
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