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Development of a subgrid model with a fine moving grid overlying a coarse Eulerian mesh for modeling reflood heat transfer.

机译:开发带有细移动网格并覆盖粗欧拉网格的子网格模型,用于对再热传递进行建模。

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摘要

One of the major uncertainties in predicting the heat transfer during core reflood which follows a hypothetical Large Break LOCA is the modeling of the phenomena occurring at the quench front.; One of the major limitations of all the current best-estimate codes is the use of a relative coarse mesh for the solution of the complex fluid flow in the quench front region in a reactor core during reflood.; The work described in this thesis is the development of a subgrid model where a Fine Hydraulic Moving Grid overlies a coarse Eulerian mesh in the proximity of the quench front and froth region. The Fine Hydraulic Moving Grid (FHMG) software package was developed and implemented into the COBRA-TF computer code. The result is a new version of the code called COBRA-TF/FHMG.; The FHMG is based on one-dimensional, three-field description of the two-phase flow in proximity of the quench front. The model includes a two-dimensional heat conduction model for the rod as well as the heat transfer from the rod surface to the fluid. The model is based on a fully implicit scheme for both heat transfer and fluid flow.; The assessment of the COBRA-TF/FHMG was performed comparing the code results against FLECHT-SEASET reflood test data. The fine hydraulic mesh, which is used in proximity of the quench front, provides a better characterization of the quench front and froth region. The quench front velocity is well predicted. However the clad temperature and the vapor temperature appear to be under predicted by the code. Further analysis showed that the current entrainment and the transition boiling models are the limitation. These models were developed based on a relatively coarse mesh and currently do not fully benefit from the additional information provided by the FHMG that better describes the evolution of the flow and heat transfer in proximity of the quench front and froth region.; The new computational model offered by the FHMG provides the framework for the development of specific phenomenological models that better characterizes the phenomena at the quench front and froth region where current models has the largest uncertainty. (Abstract shortened by UMI.)
机译:假设大断裂LOCA之后,预测岩心再驱替过程中传热的主要不确定性之一是对在急冷前沿发生的现象进行建模。当前所有最佳估计代码的主要限制之一是在驱替期间使用相对粗糙的网格来求解反应堆堆芯骤冷前沿区域中的复杂流体流。本文所描述的工作是一个子网格模型的发展,在该模型中,精细液压运动网格在急冷锋面和泡沫区域附近覆盖了较粗的欧拉网格。精细液压移动网格(FHMG)软件包已开发并实施到COBRA-TF计算机代码中。结果是该代码的新版本称为COBRA-TF / FHMG。 FHMG基于在淬火前沿附近的两相流的一维三场描述。该模型包括杆的二维热传导模型以及从杆表面到流体的热传递。该模型基于传热和流体流动的完全隐式方案。对COBRA-TF / FHMG进行评估,将代码结果与FLECHT-SEASET回注测试数据进行比较。在淬火前沿附近使用的精细液压筛网可以更好地表征淬火前沿和泡沫区域。淬火前沿速度可以很好地预测。但是,包层温度和蒸气温度似乎低于该代码预测的温度。进一步的分析表明,电流夹带和过渡沸腾模型是局限性。这些模型是基于相对粗糙的网格开发的,目前还不能完全受益于FHMG提供的附加信息,该信息可以更好地描述淬火前沿和泡沫区域附近的流动和传热过程。 FHMG提供的新计算模型为开发特定的现象学模型提供了框架,该模型可以更好地表征当前模型具有最大不确定性的淬火前沿和泡沫区域的现象。 (摘要由UMI缩短。)

著录项

  • 作者

    Frepoli, Cesare.;

  • 作者单位

    The Pennsylvania State University.;

  • 授予单位 The Pennsylvania State University.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2001
  • 页码 271 p.
  • 总页数 271
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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