Research on Performance Analysis Methods for Typical Lattice of Heat Pipe Reactors Based on the MOOSE Platform
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摘要: 为解决热管堆中全堆芯不同径向位置处典型栅元行为表征不准确的问题,基于MOOSE平台开发了典型栅元程序和MultiApp程序。典型栅元程序可实现对特定位置栅元的精细化分析,MultiApp程序可实现全堆芯计算,两者结合保证了堆芯不同径向位置处应力场、应变场和温度场计算结果的协调性和准确性。经典型栅元程序在不同边界设置下的计算结果表明,对称边界下的应力计算结果偏大,自由边界的应力结果更为合理,组合边界与周期性边界的温度计算类似,但应力结果不同。通过典型栅元程序与堆芯计算程序对比,可知自由边界下的典型栅元更能表征平功率分布稳态运行的全堆芯热力学行为。Abstract: To address the challenge of characterizing the behavior of fuel assemblies at different radial positions in heat pipe reactors, this paper develops a typical fuel assembly code and a MultiApp code based on the MOOSE platform. The typical fuel assembly code enables detailed analysis of fuel assemblies at specific positions, while the MultiApp code is capable of performing full-core calculations. The combination of the two codes ensures consistency and accuracy in calculating the stress, strain, and temperature at different radial positions. The calculation results of the typical fuel assembly code under different boundary conditions indicate that the stress calculation results are overestimated under symmetric boundary conditions, while the stress results under free boundary conditions are more reasonable. The temperature calculations under combined boundaries and periodic boundaries are similar, but the stress results are different. By comparing the typical fuel assembly code with the full-core calculation code, it is found that the typical fuel assembly under free boundary conditions has better capability to represent the thermo-mechanical behavior of the full core under steady-state operation with a uniform power distribution.
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Key words:
- MOOSE platform /
- Fuel element performance /
- Boundary conditions
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