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首页> 外文期刊>International Journal of Information Technology >CFD Simulation for Flow Behavior in Boiling Water Reactor Vessel and Upper Pool under Decommissioning Condition
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CFD Simulation for Flow Behavior in Boiling Water Reactor Vessel and Upper Pool under Decommissioning Condition

机译:退役条件下沸水反应堆容器和上水池流动特性的CFD模拟

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In order to respond the policy decision of non-nuclear homes, Tai Power Company (TPC) will provide the decommissioning project of Kuosheng Nuclear power plant (KSNPP) to meet the regulatory requirement in near future. In this study, the computational fluid dynamics (CFD) methodology has been employed to develop a flow prediction model for boiling water reactor (BWR) with upper pool under decommissioning stage. The model can be utilized to investigate the flow behavior as the vessel combined with upper pool and continuity cooling system. At normal operating condition, different parameters are obtained for the full fluid area, including velocity, mass flow, and mixing phenomenon in the reactor pressure vessel (RPV) and upper pool. Through the efforts of the study, an integrated simulation model will be developed for flow field analysis of decommissioning KSNPP under normal operating condition. It can be expected that a basis result for future analysis application of TPC can be provide from this study.
机译:为了响应无核房屋的政策决定,台电公司(TPC)将提供郭胜核电厂(KSNPP)的退役项目,以满足不久的将来的监管要求。在这项研究中,已将计算流体动力学(CFD)方法用于开发退役阶段的上池沸水反应堆(BWR)的流量预测模型。当容器与上部池和连续性冷却系统结合使用时,该模型可用于研究流动行为。在正常操作条件下,将获得整个流体区域的不同参数,包括速度,质量流量和反应堆压力容器(RPV)和上部池中的混合现象。通过此项研究,将开发一个综合仿真模型,用于在正常运行条件下对退役的KSNPP进行流场分析。可以预期,这项研究可以为TPC的未来分析应用提供基础结果。

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