基于蒙卡截面和非结构网格方法模拟JHR堆芯

Simulation of JHR reactor core based on Monte-Carlo cross-section and unstructured grid method

  • 摘要: JHR反应堆是法国正在建设的高通量试验反应堆,为现有反应堆运行、延寿和未来反应堆设计提供支持。为探索一种使用非结构网格模拟先进堆芯的方法,以简化JHR堆芯为模型,使用Gmsh程序生成堆芯非结构网格,使用蒙特卡罗程序产生多群截面,代入通用型中子扩散求解器VITAS进行计算,结果表明稳态计算参数和蒙卡程序吻合得较好。该方法对求解其他复杂先进堆芯有参考意义。

     

    Abstract:
    Background The Jules Horowitz irradiation reactor (JHR) core is a 100 MW high-flux material testing reactor under construction in southern France to support existing reactor operations, life extension, and future reactor designs. However, the complex geometry of advanced reactor cores poses significant challenges for traditional deterministic methods based on structured grids.
    Purpose In this paper, we explore and develop an unstructured grid method for simulating advanced cores, using simplified two-dimensional JHR cores without control rods as the model.
    Methods Unstructured triangular meshes were generated using the Gmsh program with varying mesh densities. The Serpent Monte Carlo code was employed to generate six-group homogenized cross sections. Steady-state neutron diffusion calculations were performed using VITAS, a general-purpose neutron diffusion solver developed by Shanghai Jiao Tong University.
    Results The effective multiplication factor (keff) calculated by VITAS converged with increasing mesh refinement, achieving agreement within 4×10−3 of the Monte Carlo reference value of 1.35958. The maximum relative deviation in assembly power distribution was within 3%, occurring at the peripheral fuel positions. The multi-group flux distributions showed good consistency between the two codes, with a maximum relative deviation of 8.6%.
    Conclusions The proposed unstructured grid method demonstrates satisfactory accuracy for steady-state analysis of complex reactor cores. This approach offers valuable reference for modeling other advanced reactors with intricate geometries where structured grids are inadequate.

     

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