首页> 外文会议>International conference on nuclear engineering;ICONE17 >PROPOSED EXPERIMENT FOR VALIDATION OF CFD METHODS FOR ADVANCED SFR DESIGN: UPPER PLENUM THERMAL STRIPING AND STRATIFICATION
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PROPOSED EXPERIMENT FOR VALIDATION OF CFD METHODS FOR ADVANCED SFR DESIGN: UPPER PLENUM THERMAL STRIPING AND STRATIFICATION

机译:验证先进SFR设计的CFD方法的拟议实验:上部气室热条和分层

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In response to the goals outlined by the U.S. Department of Energy's Advanced Fuel Cycle Initiative, an effort is underway to develop an integrated multi-physics, multi-resolution thermal-hydraulic simulation tool package for the evaluation of nuclear power plant design and safety. As part of this effort, initial guidance has been proposed for the development of experiments to supply validation data sets for the CFD-based thermo-fluid simulation capability. To demonstrate that the proposed data requirements can be achieved using current generation measurement methods and to refine correlation and data comparison methods suitable for very large data sets, an initial experiment focused on turbulent mixing in the upper plenum of an advanced sodium fast reactor has been proposed.Prior validation efforts to support the use of one-dimensional lumped parameter models in the analysis of reactor safety performance relied primarily on data from carefully scaled integral system experiments to validate and tune correlations used to represent the physics associated with a particular transient in a particular reactor design. Unlike the correlation-based lumped parameter codes, computational fluid dynamics simulations reduce the reliance on experimentally derived correlations to the prediction of local turbulence effects rather the prediction of integral quantities like pressure drop and heat transfer coefficients. As a consequence, simpler separate effects experiments, which capture the turbulence effects but not necessarily the integral effects within a specific component of a system, can be utilized as the primary validation basis for the CFD codes. However, while the need for large carefully scaled integral experiments is reduced, the high spatial and temporal resolution of these codes requires that experimental data be collected at fine spatial and temporal resolutions.An initial series of simulations has been completed to support the development of the proposed experimental facility using air as a surrogate for the sodium coolant. Design options considered in RANS simulations using the commercial CFD code Star-CCM+ include mixing facility dimensions, the number of inlet jets to be included and outlet position. The use of RANS simulations is supported by an initial benchmarking comparison with predictions from the spectral element large eddy simulation code Nek5000 for the nominal experimental geometry.
机译:为响应美国能源部高级燃料循环计划提出的目标,正在努力开发一种集成的多物理场,多分辨率的热工水力模拟工具包,用于评估核电站的设计和安全性。作为这项工作的一部分,已经提出了用于开发实验的初步指导,以提供基于CFD的热流体模拟功能的验证数据集。为了证明所提出的数据要求可以使用当前的测量方法来满足,并完善适用于非常大的数据集的相关性和数据比较方法,已提出了针对先进钠快堆反应堆上部气室中湍流混合的初步实验。 。 用于支持在反应堆安全性能分析中使用一维集总参数模型的先前验证工作主要依赖于精心缩放的积分系统实验中的数据,以验证和调整用于表示与特定反应堆中特定瞬态相关的物理学的相关性设计。与基于相关性的集总参数代码不同,计算流体动力学模拟减少了对通过实验得出的相关性对局部湍流效应的预测,而不是对诸如压降和传热系数之类的积分量的预测的依赖。因此,可以将捕获湍流效应但不一定捕获系统特定组件内的整体效应的更简单的单独效应实验用作CFD代码的主要验证基础。但是,尽管减少了对大型仔细规模的积分实验的需求,但这些代码的高时空分辨率要求以精细的时空分辨率收集实验数据。 已经完成了一系列初始模拟,以支持拟议中的实验设施的开发,该实验设施使用空气作为钠冷却剂的替代物。使用商业CFD代码Star-CCM +在RANS仿真中考虑的设计选项包括混合设施尺寸,要包括的入口射流数和出口位置。初步的基准比较与频谱元素大涡模拟代码Nek5000对标称实验几何的预测相比较,可以支持RANS仿真的使用。

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