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首页> 外文期刊>Nuclear engineering and technology >Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition
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Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition

机译:燃料-冷却剂相互作用可视化测试,用于在船上保留皮质的外部反应堆容器冷却(IVR-ERVC)

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A visualization test of the fuel–coolant interaction in the Test for Real cOrium Interaction with water (TROI) test facility was carried out. To experimentally simulate the In-Vessel corium Retention (IVR)- External Reactor Vessel Cooling (ERVC) conditions, prototypic corium was released directly into the coolant water without a free fall in a gas phase before making contact with the coolant. Corium (34.39?kg) consisting of uranium oxide and zirconium oxide with a weight ratio of 8:2 was superheated, and 22.54?kg of the 34.39?kg corium was passed through water contained in a transparent interaction vessel. An image of the corium jet behavior in the coolant was taken by a high-speed camera every millisecond. Thermocouple junctions installed in the vertical direction of the coolant were cut sequentially by the falling corium jet. It was clearly observed that the visualization image of the corium jet taken during the fuel–coolant interaction corresponded with the temperature variations in the direction of the falling melt. The corium penetrated through the coolant, and the jet leading edge velocity was 2.0?m/s. Debris smaller than 1?mm was 15% of the total weight of the debris collected after a fuel–coolant interaction test, and the mass median diameter was 2.9?mm.
机译:进行了真实的与水的铯相互作用测试(TROI)测试设施中的燃料-冷却剂相互作用的可视化测试。为了通过实验模拟容器中的氢滞留(IVR)-外部反应堆容器冷却(ERVC)条件,在与冷却剂接触之前,将原型真皮直接释放到冷却剂水中,而不会在气相中自由下落。重量比为8:2的由氧化铀和氧化锆组成的真皮(34.39?kg)过热,并使34.39?kg的真皮中的22.54?kg穿过透明相互作用容器中容纳的水。高速相机每毫秒拍摄一次冷却剂中的胶束喷射行为的图像。沿冷却液垂直方向安装的热电偶接点被下降的皮质射流依次切断。可以清楚地观察到,在燃料与冷却剂相互作用期间所拍摄的真皮射流的可视化图像与熔体下落方向上的温度变化相对应。皮质渗透到冷却液中,射流前沿速度为2.0?m / s。小于1?mm的碎片占燃料-冷却剂相互作用测试后收集的碎片总重量的15%,质量中值直径为2.9?mm。

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