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Study on the Evaluation and Simulation of Steady State Behavior and Reactor Safety Concept for Integral Pressurized Water Reactor

机译:整体压水堆稳态及反应堆安全概念评价与仿真研究

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In this study, a research has been carried out on the normal operational state concerning with the reactor under different load changes as well as simulation of pool type reactor concept by the use of thermal hydraulic system code Relap5/Mod3.4 for Integral Pressurized Water Reactors (IPWR?s). These reactors belongs to the class of small and medium sized nuclear reactors (SMR?s) and are designed in such away that most of the primary loop components are housed in a single Reactor Pressure Vessel (RPV). In this study, the reactor under study is the Inherent safe uranium zirconium hydride nuclear power reactor INSURE-100. Since, the conceptual design study phase of this reactor has been completed so the current research focuses on the normal operation which is inter related with different load characteristics as well as for the safety concept the considered reactor is simulated as a pool type. The effect of load changes on the different components of the reactor have been studied and are figure out in the graphical as well as in a parametric way. The current study also focuses on the simulation of pool type reactor concept, for this case the pressurized containment, which is partially filled with water and acts as a suppression pool. Finally the load percentage results and the steady state results obtained from the pool type reactor concept have been extracted from the graphical approach and are depicted in a parametric way and are sorted out in a table. The purpose of conducting the research is to evaluate the steady state behavior as well as safety analysis of the reactor.
机译:在这项研究中,已经通过使用热压系统代码Relap5 / Mod3.4对整体压水堆进行了研究,研究了在不同负载变化下与反应堆有关的正常运行状态,以及对池式反应堆概念的模拟。 (IPWR?s)。这些反应堆属于中小型核反应堆(SMR?s)类别,其设计应使大部分主要回路组件都容纳在单个反应堆压力容器(RPV)中。在这项研究中,正在研究的反应堆是固有的安全铀氢化锆锆核动力反应堆INSURE-100。由于该反应堆的概念设计研究阶段已经完成,因此当前的研究重点是与不同负荷特征相关的正常运行以及对于安全概念,将考虑的反应堆模拟为池型。已经研究了负载变化对反应堆不同组件的影响,并通过图形和参数方式指出了影响。当前的研究还集中在池型反应堆概念的模拟上,在这种情况下,是将部分装满水并用作抑制池的加压安全壳。最后,从池型反应堆概念中获得的负荷百分比结果和稳态结果已从图形方法中提取出来,并以参数方式进行了描述,并在表格中进行了分类。进行研究的目的是评估反应堆的稳态行为以及安全性分析。

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