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首页> 外文期刊>Nuclear Engineering and Design >Development and application of computational fluid dynamics approaches within the European project THINS for the simulation of next generation nuclear power systems
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Development and application of computational fluid dynamics approaches within the European project THINS for the simulation of next generation nuclear power systems

机译:欧洲THINS项目中用于模拟下一代核电系统的计算流体动力学方法的开发和应用

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摘要

Today computational fluid dynamics (CFD) is widely used in industrial companies, research institutes and technical safety organizations to supplement the design and analysis of diverse technical components and large systems. Such numerical programs are applied to better understand complex fluid flow and heat transfer phenomena. In the last decades there is an increasing interest in the nuclear community to utilize such advanced programs for the evaluation of different nuclear reactor safety issues, where traditional analysis tools show deficiencies. Within the FP7 European project THINS (Thermal Hydraulics of Innovative Nuclear Systems), CFD and coupled 1D-3D thermal-hydraulic simulations are being carried out. These are dedicated to the analysis of the thermal-hydraulics of gas, liquid metal and supercritical water cooled reactors. Such concepts utilize innovative fluids, which have different properties from the ones used in the current nuclear reactors. In order to improve the thermal-hydraulic predictions of their behavior, CFD development, application and validation activities are performed within THINS. This overview paper highlights some of the CFD related work within the European project. (C) 2014 Elsevier B.V. All rights reserved.
机译:如今,计算流体力学(CFD)已广泛用于工业公司,研究机构和技术安全组织,以补充各种技术组件和大型系统的设计和分析。这些数值程序可用于更好地理解复杂的流体流动和传热现象。在过去的几十年中,对于核社区而言,越来越需要利用这种高级程序来评估不同的核反应堆安全问题,而传统分析工具却显示出这些缺陷。在FP7欧洲项目THINS(创新性核系统的热工水力)中,正在执行CFD和耦合的1D-3D热工水力仿真。这些专用于分析气体,液态金属和超临界水冷反应堆的热工水力。这些概念利用了创新的流体,这些流体具有与当前核反应堆所使用的流体不同的特性。为了改善热工液压对其行为的预测,在THINS内进行了CFD开发,应用和验证活动。本概述文件重点介绍了欧洲项目中与CFD相关的一些工作。 (C)2014 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2015年第15期|13-26|共14页
  • 作者单位

    Gesell Anlagen & Reaktorsicherheit GRS mbH, Garching, Germany;

    Nucl Res & Consultancy Grp, Petten, Netherlands;

    Nucl Res & Consultancy Grp, Petten, Netherlands;

    Helmholtz Zentrum Dresden Rossendorf, Inst Fluid Dynam, Dresden, Germany;

    Univ Pisa, Pisa, Italy;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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