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Development and Assessment of CFD Models Including a Supplemental Program Code for Analyzing Buoyancy-Driven Flows Through BWR Fuel Assemblies in SFP Complete LOCA Scenarios.

机译:CFD模型的开发和评估,包括用于分析SFP完整LOCA方案中通过BWR燃料组件的浮力驱动流的补充程序代码。

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摘要

This work seeks to illustrate the potential benefits afforded by implementing aspects of fluid dynamics, especially the latest computational fluid dynamics (CFD) modeling approach, through numerical experimentation and the traditional discipline of physical experimentation to improve the calibration of the severe reactor accident analysis code, MELCOR, in one of several spent fuel pool (SFP) complete loss-ofcoolant accident (LOCA) scenarios. While the scope of experimental work performed by Sandia National Laboratories (SNL) extends well beyond that which is reasonably addressed by our allotted resources and computational time in accordance with initial project allocations to complete the report, these simulated case trials produced a significant array of supplementary high-fidelity solutions and hydraulic flow-field data in support of SNL research objectives. Results contained herein show FLUENT CFD model representations of a 9x9 BWR fuel assembly in conditions corresponding to a complete loss-of-coolant accident scenario. In addition to the CFD model developments, a MATLAB based controlvolume model was constructed to independently assess the 9x9 BWR fuel assembly under similar accident scenarios. The data produced from this work show that FLUENT CFD models are capable of resolving complex flow fields within a BWR fuel assembly in the realm of buoyancy-induced mass flow rates and that characteristic hydraulic parameters from such CFD simulations (or physical experiments) are reasonably employed in corresponding constitutive correlations for developing simplified numerical models of comparable solution accuracy.
机译:这项工作旨在通过数值实验和传统的物理实验学科来改进流体动力学,尤其是最新的计算流体力学(CFD)建模方法,以改善严重反应堆事故分析代码的标定,从而说明潜在的益处。 MELCOR,在几种乏燃料池(SFP)完全失水事故(LOCA)方案中,是其中一种。尽管桑迪亚国家实验室(SNL)进行的实验工作的范围远远超出了我们为完成报告而根据最初的项目分配所分配的资源和计算时间所合理解决的范围,但这些模拟案例试验产生了大量补充资料支持SNL研究目标的高保真解决方案和液压流场数据。本文包含的结果显示了9x9 BWR燃料组件在与完全冷却剂泄漏事故情景相对应的条件下的FLUENT CFD模型表示。除了开发CFD模型外,还构建了基于MATLAB的控制量模型,以在类似事故情况下独立评估9x9 BWR燃料组件。这项工作产生的数据表明,FLUENT CFD模型能够解决浮力引起的质量流率领域中BWR燃料组件内的复杂流场,并且合理地采用了此类CFD模拟(或物理实验)中的特征液压参数在相应的本构关系中,可以开发出具有可比性精度的简化数值模型。

著录项

  • 作者

    Artnak III, Edward Joseph.;

  • 作者单位

    The University of Texas at Austin.;

  • 授予单位 The University of Texas at Austin.;
  • 学科 Engineering Mechanical.;Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2012
  • 页码 688 p.
  • 总页数 688
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-17 11:42:39

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