首页> 外文会议>Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety Oct 15-18, 2000 Denki Bldg., Chuo-ku, Fukuoka, Japan >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:通过小直径厚壁孔的过冷水临界流速的实验研究

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摘要

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:为了研究厚孔口中的临界流动现象并生成技术数据以评估核电站中小断裂事故的断裂模拟器设计的性能,已在排污和冷凝环路中进行了临界流动测试。使用八个不同形状的厚孔口进行了稳态和排污临界流量测试。稳态流量数据表明,临界质量通量可以表示为排放系数和初始条件的函数。根据测试结果,开发了一个半经验模型。对模型预测结果和来自各种来源的测试数据进行比较后,可以准确预测通过小直径(2.0≤d≤12.7 mm)的厚孔(0.4≤L / d≤2.0)的临界质量通量。分析了两种典型的断裂模拟器的特性,它们模拟了一次小断裂冷却剂损失事故期间的断裂几何形状,并提出了针对小型测试设施的断裂模拟器设计的规定。

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