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首页> 外文期刊>Annals of nuclear energy >CFD simulating the transient thermal-hydraulic characteristics in a 17 × 17 bundle for a spent fuel pool under the loss of external cooling system accident
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CFD simulating the transient thermal-hydraulic characteristics in a 17 × 17 bundle for a spent fuel pool under the loss of external cooling system accident

机译:CFD模拟在外部冷却系统事故损失下乏燃料池中17×17束中的瞬态热工水力特性

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摘要

This paper develops a three-dimensional (3-D) transient computational fluid dynamics (CFD) model to simulate the thermal-hydraulic characteristics in a fuel bundle located in a spent fuel pool (SFP) under the loss of external cooling system accident. The SFP located in the Maanshan nuclear power plant (NPP) is selected herein. Without adopting the porous media approach usually used in the previous CFD works, this model uses a real-geometry simulation of a 17 × 17 fuel bundle, which can obtain the localized distributions of the flow and heat transfer during the accident. These distribution characteristics include several peaks in the axial distributions of flow, pressure, temperature, and Nusselt number (Nu) near the support grids, the non-uniform distribution of secondary flow, and the non-uniform temperature distribution due to flow mixing between rods, etc. According to the conditions adopted in the Procedure 597.1 (MNPP Plant Procedure 597.1, 2010) for the management of the loss-of-cooling event of the spent fuel pool in the Maanshan NPP, the temperature rising rate predicted by the present model can be equivalent to 1.26 K/h, which is the same order as that of 3.5 K/h in the this procedure. This result also confirms that the temperature rising rate used in the Procedure 597.1 for the Maanshan NPP is conservative. In addition, after the loss of external cooling system, there are about 44 h for the operator to repair the malfunctioning system or provide the alternative water source for the pool inventory to avoid the occurrence of the local boiling in the SFP based on the present predicted temperature rising rate.
机译:本文开发了三维(3-D)瞬态计算流体动力学(CFD)模型,以模拟在外部冷却系统事故损失下位于乏燃料池(SFP)中的燃料束中的热工液压特性。本文选择了位于马鞍山核电厂(NPP)的SFP。该模型不采用以前的CFD工作中通常使用的多孔介质方法,而是使用17×17燃料束的真实几何模拟,可以获取事故期间流动和传热的局部分布。这些分布特征包括支撑网格附近的轴向,流量,压力,温度和Nusselt数(Nu)的轴向分布中的多个峰值,二次流的不均匀分布以及由于杆之间的流动混合而引起的温度不均匀根据程序597.1(MNPP工厂程序597.1,2010)中用于处理马鞍山核电厂乏燃料池冷却损失事件的条件,本模型预测的升温速率可以等于1.26 K / h,与此过程中3.5 K / h的顺序相同。该结果也证实了,马鞍山核电厂在程序597.1中使用的升温速率是保守的。此外,在失去外部冷却系统后,操作人员大约需要44小时来维修故障系统或为水池存货提供替代水源,以避免根据目前的预测在SFP中发生局部沸腾温升率。

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  • 来源
    《Annals of nuclear energy》 |2014年第11期|241-249|共9页
  • 作者单位

    Taiwan Power Company, Taiwan, ROC,Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, Taiwan, ROC;

    Department of Engineering and System Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, Taiwan, ROC;

    Department of Engineering and System Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, Taiwan, ROC,Department of Mechanical and Biomedical Engineering, City University of Hong Kong, Tat Chee Avenue, Kowloon, Hong Kong;

    Department of Engineering and System Science, Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, Taiwan, ROC,Department of Mechanical and Biomedical Engineering, City University of Hong Kong, Tat Chee Avenue, Kowloon, Hong Kong;

    Institute of Nuclear Engineering and Science, National Tsing Hua University, 101, Sec. 2. Kuang-Fu Rd., Hsingchu 30013, Taiwan, ROC;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Spent fuel pool; 3-D transient CFD; Loss of external cooling system accident;

    机译:乏燃料池;3D瞬态CFD;失去外部冷却系统事故;

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