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THERMAL HYDRAULIC PERFORMANCE ANALYSIS FOR PASSIVE CONTAINMENT COOLING SYSTEM OF AP1000 IN THE EVENT OF LOCA

机译:一次LOCA下AP1000被动式冷却系统的热工水力性能分析。

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The design of a nuclear reactor containment building is of key importance in order to enhance the safety of a nuclear power plant. Owing to nuclear accidents such as TMI, Chernobyl and Fukushima, more and more attention is paid to the passive concept in nuclear power development. In order to improve the safety of new generation nuclear power plant, passive systems are widely used, passive containment cooling system in AP1000 is one of the typical example of such kinds of systems. It's function is to transfer the heat produced in the containment to the atmosphere and keep the pressure in the vessel below the threshold under such accidents as Loss of coolant (LOC A), main steam line break (MSLB), etc. The system operates based on natural circulations inside the steel vessel and in the air baffle outside the containment, and the cooling water is sprayed to the steel surface to enhance the heat transfer process. A proper model simulating the system behavior is needed for system design and safety analysis, and a multivolume lumped parameter approach is employed in order to analyze the containment integrity and to study the long term response of postulated Loss of coolant (LOCA) accidents and Main steam line break (MSLB) accidents. However, the temperature and pressure distributions cannot be described detailed by such model, which is important to study the T-H characteristics in the containment. In this paper LOCA has been simulated on MATLAB using a given pipe break size and the response of containment is analyzed. Furthermore, the results are compared with the results in the Westinghouse Design Control Document 2002. Then the thermal hydraulic performance is studied, the factors such as the air temperature, containment pressure and mass flow rate of the coolant and their effects on the containment are analyzed. This research is done to get further insight on the safety analysis of reactor containment regarding maximum temperature and stress calculation inside the containment.
机译:核反应堆安全壳建筑的设计对于提高核电厂的安全至关重要。由于TMI,切尔诺贝利和福岛等核事故的发生,越来越多的人将目光投向了核电发展中的无源概念。为了提高新一代核电站的安全性,无源系统得到了广泛的应用,AP1000中的无源安全壳冷却系统就是这类系统的典型例子之一。它的功能是将安全壳中产生的热量传递到大气中,并在发生冷却剂损失(LOC A),主蒸汽管线中断(MSLB)等事故的情况下,将容器中的压力保持在阈值以下。在钢制容器内部以及安全壳外部的空气挡板中的自然循环中,冷却水被喷洒到钢制表面,以增强传热过程。为了进行系统设计和安全分析,需要一个合适的模拟系统行为的模型,并采用多体积集总参数方法来分析安全壳的完整性并研究假定的冷却剂损失(LOCA)事故和主蒸汽的长期响应换行(MSLB)事故。但是,这种模型无法详细描述温度和压力分布,这对于研究安全壳中的T-H特性很重要。在本文中,使用给定的管道中断尺寸在MATLAB上模拟了LOCA,并分析了安全壳的响应。此外,将结果与2002年《西屋设计控制文件》中的结果进行比较。然后研究热工水力性能,分析诸如空气温度,安全壳压力和冷却剂质量流量等因素及其对安全壳的影响。 。进行这项研究的目的是为了进一步了解反应堆安全壳关于安全壳内部的最高温度和应力计算的安全性分析。

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