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Development of Fuel Performance Analysis Code for Liquid Metal Coole Fast Reactor Based on MOOSE Platform

  • Shihao Shao,
  • Zhouyu Liu,
  • Xiaobei Xu,
  • Yufan Zong,
  • Liangzhi Cao,
  • Hongchun Wu

摘要

The liquid metal cooled fast reactor is of great strategic significance for the innovative development of nuclear energy in China, and the development of fuel performance analysis programs suitable for it is of great significance for the design and safety analysis of fast reactors. This article is based on the multi physics coupling platform MOOSE and finite element method, and independently developed the fuel performance analysis program LoongCALF for liquid metal cooled fast reactors. The program adopts a 1.5-dimensional modeling method to perform multi-physical field coupling calculations on the fuel rods, which uses a single-layer thermal-mechanical module and a global gas behavior module. The program is suitable for fast reactor fuel elements with MOX and HT-9 cladding. For the calculation example of a complete fuel rod whose pellet material is MOX and cladding material is HT-9, LoongCALF program and China Institute of Atomic Energy program are respectively used to model and calculate the calculation example, and the calculation results are compared. The results indicate that the LoongCALF program can accurately simulate the spatial distribution and temporal variation of key physical parameters inside fuel elements under steady-state operating conditions of liquid metal cooled fast reactors.