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EXPERIMENTAL ANALYSIS OF CONTAINMENT ATMOSPHERE MIXING AND STRATIFICATION INDUCED BY VERTICAL FLUID RELEASE

机译:垂直流体释放引起的大气混合与分层的实验分析

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Continuing safety assessments are important for the present and future generations of nuclear reactors to ensure safe and efficient use of nuclear energy. For safety analysis purpose, lumped parameter codes as well as codes with 3D capabilities are used to predict and simulate the containment conditions following a hypothetical accident. The assessment of code capability to predict consequences of hypothetical accidents can be done by comparing code simulations with experimental data obtained in large scale facilities under prototypical thermal hydraulic conditions. The large scale PANDA test facility built at the Paul Scherrer Institute (PSI) in Switzerland is well suited to perform thermal hydraulic experiments for investigating integral containment system response during accidents and also to study multi-compartmental 3D effects related to a Light Water Reactor (LWR).This paper presents the experimental results and the analysis of two tests performed in a containment that is represented by two large vessels (volume of each vessel is 90 m~3) interconnected by a bended pipe of 1 m diameter. The tests address the possibility of the permanence of hydrogen stratification just beneath the containment dome under conditions determined by low velocity and a plume or jet of higher density which could be, for instance, due to steam produced by evaporation of the sump. Since practically no data are available on these specific phenomena in largescale test facilities, the capabilities of the codes could not be yet verified.During the experiments, a stratified helium-rich layer is created in upper part of one of the two vessels and thereafter, interaction of an ascending buoyant jet with the stratified helium layer is investigated. Helium is used to simulate hydrogen released by cladding metal water reaction. Two tests with initial densimetric Froude number equal to 22.6 (Test_(Air/He)) and 104 (Tests_(Steam/He)) are investigated. The distance between the pipe exit for vertical injection of the fluid and the bottom front of the stratified helium rich layer is about 2m for both the investigated test cases. Results depicting the mixing of lower and upper vessel regions are presented in terms of helium concentration profiles and temperature contour maps. The results show that the maximum penetration height is controlled by the initial exit conditions (momentum flux and the buoyancy flux) and density stratification inside the test vessel. Additionally, for the given test conditions and geometry, most of the injected fluid remains trapped in upper part of one of the two test vessels in which helium layer is created.
机译:持续的安全评估对于今世后代的核反应堆至关重要,以确保安全有效地利用核能。出于安全分析的目的,集总参数代码以及具有3D功能的代码用于预测和模拟假设性事故后的收容条件。可以通过将代码模拟与在典型热水力条件下在大型设施中获得的实验数据进行比较,来进行预测假想事故后果的代码能力的评估。瑞士Paul Scherrer研究所(PSI)建造的大型PANDA测试设施非常适合进行热力水力实验,以研究事故期间的整体安全壳系统响应,还可以研究与轻水反应堆(LWR)相关的多隔室3D效应)。 本文介绍了在一个以一个直径为1 m的弯管相互连接的两个大容器(每个容器的体积为90 m〜3)为代表的密闭容器中进行的两次试验的实验结果和分析。这些测试解决了在低速和较高密度的羽流或喷射流所确定的条件下,氢弹分层永久存在于安全壳穹顶下方的可能性,例如可能是由于贮槽蒸发产生的蒸汽。由于实际上没有关于这些特定现象的大量数据 规模的测试设施,尚无法验证代码的功能。 在实验过程中,在两个容器之一的上部形成了分层的富氦层,然后研究了上升的浮力射流与分层的氦层的相互作用。氦气用于模拟金属熔覆金属水反应释放的氢。研究了两个初始密度弗洛德数等于22.6(Test_(Air / He))和104(Tests_(Steam / He))的测试。对于两个已研究的测试案例,用于垂直注入流体的管道出口与分层富氦层底端之间的距离约为2m。根据氦气浓度分布图和温度轮廓图显示了描绘下部和上部血管区域混合的结果。结果表明,最大穿透高度由初始出口条件(动量通量和浮力通量)和测试容器内部的密度分层控制。另外,对于给定的测试条件和几何形状,大多数注入的流体仍被捕获在两个测试容器之一的上部,在其中形成了氦层。

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