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Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

机译:基于经验相关性和CFD模拟的蒸汽凝结模拟蒸汽凝结的流体对流体缩放标准的间接验证

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摘要

Several nuclear reactor designs have adopted passive safety systems with condensation inside horizontal tubes, such as the Passive Auxiliary Feedwater System (PAFS) of the APR+, the new generation of the Korean-Standard Pressurized Water Reactors (PWR). Performing steam condensation experiments under high-pressure conditions is needed for the design and the realistic prediction of the condensation phenomena in such systems. To avoid the costs and technical complexities associated with experimentation at high-pressure conditions, a fluid-to-fluid scaling method to model high-pressure steam condensation with a simulant fluid, refrigerant for instance, had been developed. It was determined that the liquid-to-vapor density ratio, the Froude number, and the vapor Reynolds number should be preserved in order to guarantee the flow regime and heat transfer similarity between prototypes and models. The scope of the current work is to validate the developed scaling criteria. Due to the limitation of test data of different fluids with comparable test parameters, indirect validation is proposed based on two approaches. The first approach is based on empirical correlations, in which test data from one fluid are transferred to the equivalent conditions of the other fluid, the transferred data are then compared with condensation correlations to check the validity of the scaling method. The second approach is based on CFD calculations. A CFD model, using the commercial CFD code STAR-CCM+, for the simulation of condensation in hotizontal tubes is developed. The Fluid Film model is used for modeling the condensate film thickness and development. For modeling the phase change process, source and sink terms are introduced to the continuity, momentum, and energy equations at the interface between the vapor and the condensate film. The developed CFD model is then applied in the scaling criteria validation by using it to simulate the condensation phenomena of different models in one fluid and compare its results with the corresponding experimental data in other fluid. The validation results show good agreement between prototypes and their equivalent models, and show good feasibility and reasonable accuracy of the proposed scaling criteria.
机译:若干核反应堆设计采用了无源安全系统,卧式管内的冷凝,例如APR +的被动辅助给水系统(PAF),新一代韩国标准加压水反应堆(PWR)。在这种系统中的设计和凝结现象的设计和现实预测需要在高压条件下进行蒸汽冷凝实验。为避免与高压条件下的实验相关的成本和技术复杂性,已经开发了一种用于模拟高压蒸汽冷凝的流体流体缩放方法,例如,例如,已经开发了模拟液,制冷剂的制冷剂。应确定液到蒸汽密度比,FRoude号和蒸气雷诺数应保留,以保证原型和模型之间的流动状态和传热相似。当前工作的范围是验证发达的缩放标准。由于具有可比测试参数的不同流体的测试数据的限制,基于两种方法提出了间接验证。第一方法基于经验相关性,其中来自一个流体的测试数据被转移到另一个流体的等同条件,然后将转移的数据与冷凝相关性进行比较,以检查缩放方法的有效性。第二种方法是基于CFD计算。开发了一种CFD模型,使用商业CFD码Star-CCM +进行仿真,用于仿真Hotizontal管中的冷凝。流体膜模型用于建模冷凝水膜厚度和显影。为了对蒸汽和冷凝物膜之间的界面处的连续性,动量和能量方程引入源和水槽术语。然后,通过使用它在缩放标准验证中应用开发的CFD模型以模拟一个流体中不同模型的冷凝现象,并将其结果与其他流体中的相应实验数据进行比较。验证结果在原型和其等效模型之间表现出良好的一致性,并表现出良好的可行性和合理的准确性,提出的缩放标准。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2021年第7期|111235.1-111235.17|共17页
  • 作者单位

    Korea Adv Inst Sci & Technol KAIST Dept Nucl & Quantum Engn 291 Daehak Ro Daejeon 34141 South Korea;

    Korea Adv Inst Sci & Technol KAIST Dept Nucl & Quantum Engn 291 Daehak Ro Daejeon 34141 South Korea;

  • 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
  • 中图分类
  • 关键词

  • 入库时间 2022-08-19 02:29:27

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