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管内顶部骤冷过程中骤冷前沿推进速度实验研究 被引量:3

EXPERIMENTAL INVESTIGATION ON THE PROGRESSING VELOCITY OF QUENCH FRONT DURING THE TOP QUENCHING IN A VERTICAL TUBE
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摘要 采用瞬态热块实验技术和非稳态二维数值分析方法研究了低压低质量流速条件下竖直管内顶部骤冷过程中骤冷前沿的推进特性。以理论模型和理论关系式为基础,通过详细的参数敏感性分析引入流动参数的影响特征,得到了本文实验条件下的骤冷前沿推进速度的半经验关系式,与实验数据及相应的其它关系式的比较结果表明本文的半经验关系式在模型结构和预测精度等方面均有较大的提高。实验条件如下:15×1.51Cr18Ni9Ti元件管;系统压力:0.31~0.88MPa;质量流速:17.7—902.0kg/m2·s;入口过冷度:3℃—77℃;初始热壁温度:450℃—600℃。本文的研究可为同类问题的工程研究和应用提供指导。 An experimental investigation on the progressing velocity of quench front during the top quenching in a vertical tube under low pressure and low mass flux was presented by the transient hot patch quenching test technique and unsteady state two dimensional numerical method in high pressure and high temperature water loop of reactor thermalhydaulic laboratory, NPIC. Based on the theoretical models and correlations, a semi empirical correlation, containing the effect of flow parameters by some detailed parameter sensitivity analysises, was obtained. In comparison with the experimental data and other correlations, the model structure and predicted accuracy of the correlation developed in this paper gave better results, with the following experimental conditions: φ 15×1.5 mm 1Cr18Ni9Ti element tube; system pressure:0.31-0.88 MPa; mass flux:17.7-902 kg/m 2·s; inlet subcooling:3-77℃; initial hot wall temperature:450-600℃.
出处 《核科学与工程》 CSCD 北大核心 1998年第2期109-118,共10页 Nuclear Science and Engineering
基金 中国核动力研究设计院青年科学研究基金
关键词 骤冷 顶部淹没 骤冷前沿推进速度 反应堆安全分析 quenching top reflooding progressing velocity of quench front safety analysis of reactor
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  • 1黄彦平,中国核动力研究设计院报告,1996年

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