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燃料元件在热冲击下基于ANSYS的动态响应仿真
引用本文:梁文峰,邱东,杨成德,范晓强,谢奇林,尹延朋.燃料元件在热冲击下基于ANSYS的动态响应仿真[J].科学技术与工程,2014,14(20).
作者姓名:梁文峰  邱东  杨成德  范晓强  谢奇林  尹延朋
作者单位:中国工程物理研究院核物理与化学研究所,中国工程物理研究院核物理与化学研究所,中国工程物理研究院核物理与化学研究所,中国工程物理研究院核物理与化学研究所,中国工程物理研究院核物理与化学研究所,中国工程物理研究院核物理与化学研究所
基金项目:国家自然科学基金项目(批准号:11205139和11305152);中国工程物理研究院科技发展基金项目(批准号:2012A0103002和2012B0103006).
摘    要:燃料元件中裂变引起的热冲击应力是核临界安全研究的重要内容。采用ANSYS有限元程序中的二维plane182、plane183和三维solid187、solid45单元模型对脉冲加热的铀钼合金厚壁球壳进行了仿真,以一维热弹性力学方程的数值解为基准获得了不同模型计算误差。与国外用于核反应堆工程设计和研究的程序相比,采用plane183或solid187模型因能更严格地满足理论边界条件,具有更小的计算误差。这些结果为进一步开展核反应堆瞬态过程研究以及燃料元件设计提供了参考。

关 键 词:热冲击  核临界安全  ANSYS  动态仿真
收稿时间:2014/2/22 0:00:00
修稿时间:2014/3/17 0:00:00

Dynamic response simulation of the fuel component under thermal shock with ANSYS
LIANG Wen-feng,QIU Dong,YANG Cheng-de,FAN Xiao-qiang,XIE Qi-lin and YIN Yan-peng.Dynamic response simulation of the fuel component under thermal shock with ANSYS[J].Science Technology and Engineering,2014,14(20).
Authors:LIANG Wen-feng  QIU Dong  YANG Cheng-de  FAN Xiao-qiang  XIE Qi-lin and YIN Yan-peng
Institution:Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics,Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics,Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics,Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics,Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics
Abstract:] Thermal shock stress due to fission in fuel component is an important issue in nuclear criticality safety study. A pulse-heated thick-walled hollow sphere of Uranium-Molybdenum alloy was simulated with ANSYS finite element program, and typical two-dimensional plane182, plane183 and typical three-dimensional solid187, solid45 element models were adopted. The dynamic properties obtained were benchmarked to the numerical solution of one-dimensional thermo elastic equation, and the computational errors of different models were determined. Compared with the codes dedicated to the engineering design and study of the nuclear reactors, enhanced accuracy can be obtained by adopting plane183 or solid187 ANSYS element models as they agree well with the theoretical boundary conditions. The results are of reference value for further study of the transient process in nuclear reactors and for the design of fuel components.
Keywords:Thermal shock  Nuclear criticality safety  ANSYS  Dynamic simulation
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