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Experimental study and modelling of liquid ejection through orifices by sparging gas

机译:喷射气体通过孔口喷射液体的实验研究和建模

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Corium coolability after a severe PWR accident involving core meltdown and RPV failure is one of the main issues in nuclear safety. The case considered here is a situation in which the corium is assumed to spread over a concrete floor and is flooded by water. In this framework, many research efforts are performed to study the physical phenomena, which may enhance the heat transfer between the corium and the water pool. Among these phenomena, melt entrainment above the corium crust by the sparging gas, released by the concrete ablation appears to be a potentially efficient cooling mechanism. The main target of the PERCOLA experimental program is to provide qualitative and quantitative information on this entrainment phenomenon. It consists in analytical tests performed with simulant materials of increasing viscosity to simulate the enrichment of the corium in SiO_2 during the MCCI. After a short reminder about the assessment of the efficiency of the ejection mechanism, the second part of this paper is devoted to a general description of the test program and to the presentation of the main results. In the last part, attention focuses on modelling the liquid entrainment phenomenon and on comparison between the experimental data and the calculation results of two different entrainment models.
机译:严重的PWR事故(包括堆芯熔化和RPV失效)后的皮质冷却能力是核安全的主要问题之一。此处考虑的情况是一种情况,其中假定皮质纤维散布在混凝土地板上并被水淹没。在此框架下,进行了许多研究工作来研究物理现象,这可能会增强真皮与水池之间的热传递。在这些现象中,由混凝土烧蚀释放出的鼓泡气体将熔融夹带带到了皮壳上方,这似乎是一种潜在的有效冷却机制。 PERCOLA实验程序的主要目标是提供有关这种夹带现象的定性和定量信息。它包括对粘度增加的模拟材料进行的分析测试,以模拟MCCI过程中SiO_2中的Cor富集。在简短回顾一下弹出机制的效率评估之后,本文的第二部分专门介绍了测试程序,并介绍了主要结果。在最后一部分中,注意力集中在液体夹带现象的建模上,以及实验数据和两种不同夹带模型的计算结果之间的比较。

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