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Transient two-phase flow and application to severe nuclear reactor accident.

机译:瞬态两相流及其在核反应堆严重事故中的应用。

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摘要

The present research is to study the transient two-phase flow in the postulated Direct Containment Heating reactor accident. The corium dispersion phenomenon in the accident scenario is investigated both experimentally and analytically. In addition, a non-linear stability criterion is developed for the separated two-phase flow in a horizontal channel, resulting in a more accurate flow regime transition criterion for the flow in the reactor cavity. For the DCH simulation experiments, a capacitance probe for liquid metal film thickness measurement is developed. It is a plate type electrode coated with insulating paint, and the film thickness is measured via the capacitance of the coating immersed in the film flow. A test facility with 1:10 scale of the Zion reactor geometry is designed and constructed for the DCH separate effect experiments. The tests are conducted under 1.4 MPa to 14.2 MPa vessel pressure with water or woods metal to simulate the corium. The parameters for theoretical analysis are obtained with various instruments. These include the size and size distribution of the dispersed droplets, the liquid film thickness and velocity in the cavity, and the pressure transient at different locations. Based on experimental results, a mechanistic model is developed for the corium dispersion process. In this model, the accident transient is divided into four stages: (1) liquid and gas blow-down, (2) liquid film flow in the cavity before gas discharge, (3) liquid and gas flow in the cavity, and (4) droplet transport and re-entrainment in the subcompartment. In each stage, the flow is modeled with the dominant driving mechanism. Consequently, the droplet dispersion and the mean droplet size in the containment are predicted. Compared to the experimental data, fairly good agreement is achieved. To help the modeling, the interfacial wave stability problem is investigated with wave front perturbation method. A wave stability criterion is obtained with weakly non-linear effects. Moreover, the types of the unstable waves, under-cut wave and roll wave, are predicted from the non-linear term.
机译:本研究旨在研究假定的直接安全壳加热反应堆事故中的瞬态两相流。通过实验和分析研究了事故情况下的钙弥散现象。此外,针对水平通道中分离的两相流建立了非线性稳定性判据,从而为反应堆腔体内的流提供了更为精确的流态转换判据。对于DCH模拟实验,开发了一种用于测量液态金属膜厚度的电容探头。它是一种涂有绝缘涂料的平板型电极,通过浸入薄膜流中的涂层的电容来测量薄膜厚度。设计并构建了具有1:10比例的Zion反应堆几何形状的测试设施,用于DCH分离效应实验。该测试是在1.4 MPa至14.2 MPa的容器压力下用水或木材金属进行的,以模拟皮质。使用各种仪器可以获得用于理论分析的参数。这些因素包括分散液滴的大小和大小分布,空腔中的液膜厚度和速度以及不同位置的瞬态压力。根据实验结果,建立了一种用于钙分散过程的机理模型。在该模型中,事故瞬变分为四个阶段:(1)液体和气体的吹扫;(2)气体在排出之前在腔中的液膜流动;(3)腔中的液体和气体流动;以及(4) )小室中的液滴运输和重新夹带。在每个阶段,均使用主导驱动机制对流程进行建模。因此,可以预测容器中的液滴散布和平均液滴尺寸。与实验数据相比,取得了很好的一致性。为了帮助建模,采用波前摄动法研究了界面波稳定性问题。获得了具有弱非线性效应的波浪稳定性判据。此外,根据非线性项预测了不稳定波的类型,底切波和侧倾波。

著录项

  • 作者

    Wu, Qiao.;

  • 作者单位

    Purdue University.;

  • 授予单位 Purdue University.;
  • 学科 Engineering Nuclear.; Engineering Mechanical.
  • 学位 Ph.D.
  • 年度 1995
  • 页码 270 p.
  • 总页数 270
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;机械、仪表工业;
  • 关键词

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