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3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition

机译:3D辐照条件下板型核燃料组件的流体固体耦合仿真

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摘要

In this study, a three-dimensional (3D) fluid-solid coupling simulation with the full consideration of irradiation effects for plate-type nuclear fuel assemblies was conducted. Mechanical models of radiation-induced deformations in solid domain and thermo-hydraulic models in fluid domain were established based on ABAQUS and FLUENT, respectively. By use of MpCCI, the capability of fluid-solid coupling simulation was developed through the real-time parameter exchange of different physical fields at fluid-solid boundary interfaces. The accuracy and reliability of fluid-solid coupling methodology by FLUENT-MpCCI-ABAQUS was validated through benchmark with simulation in public reference. The influence of radiation swelling and bending deformation on fluid thermal-hydraulic characteristics was investigated based on the developed coupling analysis method. In addition, the sensitivity study of heterogeneous swelling and flow channel width was carried out. The simulation result shows that radiation swelling and bending deformation exerted substantial influence on flow distribution and outlet temperature.
机译:在该研究中,进行了一种具有完全考虑板式核燃料组件的照射效应的三维(3D)流体固体耦合模拟。基于ABAQUS和流利的流体域中固体结构域和热液压模型中的辐射诱导变形的机械模型。通过使用MPCCI,通过流体 - 固体边界接口处的不同物理领域的实时参数交换来开发流体固体耦合仿真的能力。通过在公开参考中的模拟的基准测试通过基准验证流体 - MPCCI-ABAQUS的液固耦合方法的准确性和可靠性。基于开发的耦合分析方法研究了辐射膨胀和弯曲变形对流体热液压特性的影响。此外,进行了异质膨胀和流动通道宽度的敏感性研究。仿真结果表明,辐射膨胀和弯曲变形施加对流量分布和出口温度的显着影响。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2020年第8期|103428.1-103428.22|共22页
  • 作者单位

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Shaanxi Key Lab Adv Nucl Energy & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Shaanxi Key Lab Adv Nucl Energy & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Minist Ecol & Environm Peoples Republ China Nucl & Radiat Safety Ctr Beijing 100082 Peoples R China;

    Shenzhen Univ Coll Phys & Optoelect Engn Shenzhen 518060 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Shaanxi Key Lab Adv Nucl Energy & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Shaanxi Key Lab Adv Nucl Energy & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Shaanxi Key Lab Adv Nucl Energy & Technol State Key Lab Multiphase Flow Power Engn Xian 710049 Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Plate-type nuclear fuel; Fluid-solid coupling analysis; Fuel behavior analysis;

    机译:板式核燃料;流体固耦合分析;燃料行为分析;

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