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Analyzing the alternative shutdown cooling behaviors for Chinshan Nuclear Power Plant using CFD simulation

机译:使用CFD仿真分析金山核电厂的替代性停机冷却行为

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摘要

The Chinshan Nuclear Power Plant (CSNPP) is a GE-designed BWR4 plant, having two identical units with rated core thermal power of 1804 MWt each unit. Several alternative shutdown cooling methods driven by natural or mixed convection has been proposed by the plant for studying the core cooling capability when the Residual Heat Removal (RHR) systems are not available or the refueling tasks, such as the In Vessel Visual Inspection (IWI) work etc., is being proceeded. One of the examples is to connect a pipe from the outlet of the new spent fuel heat exchanger to the reactor cavity. The design of the alternatives shall ensure that the maximum core fluid temperature is limited below the boiling temperature of water. In this study, a Computational Fluid Dynamics (CFD) model is developed to analyze the natural convection phenomena during the shutdown period. Through a series of assumption, modeling and meshing processes, a calculation domain with approximate four million meshes including the RPV, reactor cavity and spent fuel pool, have been solved in this study. The analysis results showed that the passive alternative shutdown cooling system could provide sufficient heat removal capability to maintain the maximum core fluid temperature below boiling temperature. The results also indicated that the alternative shutdown cooling system could be served as an appropriate solution for CSNPP when the RHR is inoperable.
机译:金山核电厂(CSNPP)是GE设计的BWR4电厂,具有两个相同的单元,每个单元的额定核心热功率为1804 MWt。工厂已经提出了几种由自然对流或混合对流驱动的停机冷却方法,用于研究无余热(RHR)系统或加油任务时的核心冷却能力,例如船上目视检查(IWI)工作等。示例之一是将管道从新的乏燃料热交换器的出口连接到反应堆腔室。替代方案的设计应确保最大堆芯流体温度限制在水的沸腾温度以下。在这项研究中,建立了计算流体动力学(CFD)模型来分析停机期间的自然对流现象。通过一系列假设,建模和网格划分过程,该研究解决了一个包含大约400万个网格划分的计算域,包括RPV,反应堆空腔和乏燃料池。分析结果表明,被动备用停机冷却系统可提供足够的排热能力,以将最大堆芯流体温度保持在沸腾温度以下。结果还表明,当RHR无法运行时,备用停机冷却系统可作为CSNPP的适当解决方案。

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