首页> 外文会议>Japan-Korea symposium on nuclear thermal hydraulics and safety >AN EXPERIMENTAL INVESTIGATION OF CRITICAL FLOW RATES OF SUBCOOLED WATER THROUGH A THICK ORIFICE WITH A SMALL DIAMETER
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AN EXPERIMENTAL INVESTIGATION OF CRITICAL FLOW RATES OF SUBCOOLED WATER THROUGH A THICK ORIFICE WITH A SMALL DIAMETER

机译:小直径厚孔临界水临界流速的实验研究

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To study critical flow phenomenon in a thick orifice, and to generate technical data to evaluate the performance of break simulator design for small break accidents in a nuclear power plant, critical flow tests have been performed at the Blowdown and Condensation Loop. Steady state and blowdown critical flow tests have been performed using eight different-shaped thick orifices. The steady state flow data show that the critical mass flux can be expressed as a function of the discharge coefficient and initial conditions. Based upon the test results, a semi-empirical model has been developed. Comparison between the model prediction and test data from various sources showed that the critical mass flux through a thick orifice (0.4 ≤ L/d ≤ 2.0) with a small diameter (2.0 ≤ d ≤ 12.7 mm) can be accurately predicted. The characteristics of two typical break simulators, which simulate break geometries during a small break loss-of-coolant-accident, were analyzed and provisions for the design of a break simulator for a small scale test facility have been suggested.
机译:为了研究厚孔中的临界流动现象,并产生技术数据以评估核电厂中的小休息事故的中断模拟器设计的性能,在排污和冷凝环中进行了临界流动测试。使用八种不同形状的厚孔进行稳态和排污临界流动测试。稳态流量数据表明,临界质量磁通可以表示为放电系数和初始条件的函数。基于测试结果,开发了半实证模型。来自各种源的模型预测和测试数据之间的比较显示,可以精确地预测通过厚孔(0.4≤L/d≤2.7mm)的临界质量磁通量(0.4≤L/d≤2.7mm)。两种典型中断模拟器的特点,其在小休息丧失的冷却液发生过程中模拟了破坏几何形状,并提出了用于小规模测试设施的断裂模拟器设计的规定。

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