In this paper, we present a formal Fourier analysis (FA) of Picard iteration for the coupled neutronics/thermal hydraulics (N/TH) problem and derive theoretical predictions for the spectral radius of Picard iteration for such coupled calculations as a function of the temperature difference between the fuel and coolant, temperature coefficients of cross sections (i.e., Doppler feedback), scattering ratio, and core height. An optimal underrelaxation factor is also derived based on the Fourier analysis.
翻译:在本文中,我们提出正式的Fourier对中子/热液压(N/TH)结合问题的Picard迭代问题进行正式的Fourier分析,并得出对Picard迭代(N/TH)光谱半径的理论预测,作为燃料和冷却剂之间的温度差、跨区块的温度系数(即多普勒反馈)、散射率和核心高度的函数的计算。