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Non-Local Equilibrium Two-phase Flow model With Phase Change In Porous Media And Its Application To Reflooding Of a Severely Damaged Reactor Core

机译:多孔介质相变的非局部平衡两相流动模型及其在严重受损反应堆芯的reshod中的应用

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A generalized non local-equilibrium, three-equation model was developed for the macroscopic description of two-phase flow heat and mass transfer in porous media subjected to phase change. Six pore-scale closure problems were proposed to determine all the effective transport coefficients for representative unit cells. An improved model is presented in this paper with the perspective of application to intense boiling phenomena. The objective of this paper is to present application of this model to the simulation of reflooding of severely damaged nuclear reactor cores. In case of accident at a nuclear power plant, water sources may not be available for a long period of time and the core heats up due to the residual power. Any attempt to inject water during core degradation can lead to quenching and further fragmentation of the core material. The fragmentation of fuel rods and melting of reactor core materials may result in the formation of a "debris bed". The typical particle size in a debris bed might reach few millimeters (characteristic length-scale: 1 to 5 mm), which corresponds to a high permeability porous medium. The proposed two-phase flow model is implemented in the ICARE-CATHARE code, developed by IRSN to study severe accident scenarios in pressurized water reactors. Currently, the French IRSN has set up two experimental facilities to study debris bed reflooding, PEARL and PRELUDE, with the objective to validate safety models. The PRELUDE program studies the complex two phase flow of water and steam in a porous medium (diameter 180 mm, height 200 mm), initially heated to a high temperature (400°C or 700°C). The series of PRELUDE experiments achieved in 2010 constitute a significant complement to the database of high temperature bottom reflood experimental data. They provide relevant data to understand the progression of the quench front and the intensity of heat transfer. Modeling accurately these experiments required improvements to the reflooding model, especially in terms of the existence of various saturation regimes. The improved two-phase flow model shows a good agreement with PRELUDE experimental results.
机译:开发了广泛的非局部平衡,三方程模型用于对经受相变的多孔介质中的两相流流热和质量传递的宏观描述。提出了六个孔隙率闭合问题以确定代表性单位细胞的所有有效传输系数。本文提出了一种改进的模型,其应用于激烈的沸腾现象。本文的目的是展示该模型在模拟严重损坏的核反应堆核心的模拟。在核电厂发生事故的情况下,长时间可能无法使用水源,并且由于剩余动力,核心升温。在核心降解期间注入水的任何尝试都会导致芯材料的淬火和进一步的破碎。燃料棒的碎片和反应器芯材料的熔化可能导致形成“碎片床”。碎片床中的典型粒度可能达到几毫米(特征长度:1至5mm),其对应于高渗透性多孔介质。所提出的两相流模型是在ICare-Cathare Code中实施的,由IRSN开发,以研究加压水反应堆中的严重事故情景。目前,法国IRSN建立了两种实验设施,可以研究碎片床,珍珠和前奏,目的是验证安全模型。前列程序研究了多孔介质(直径180mm,高度200mm)中的水和蒸汽的复杂两相流,最初加热至高温(400℃或700℃)。在2010年实现的一系列前列实验构成了高温底部的高温底部的数据库的重要补充。它们提供相关数据以了解淬火前沿的进展和传热强度。准确建模这些实验需要改进反射模型,特别是在存在各​​种饱和度方案方面。改进的两相流模型与前列实验结果显示出良好的一致性。

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