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Optimized Eigenvalue Solvers for the Neutron Transport Equation

机译:中子输运方程的优化特征值求解器

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A discrete ordinates method has been developed to approximate the neutron transport equation for the computation of the lambda modes of a given configuration of a nuclear reactor core. This method is based on discrete ordinates method for the angular discretization, resulting in a very large and sparse algebraic generalized eigenvalue problem. The computation of the dominant eigenvalue of this problem and its corresponding eigenfunction has been done with a matrix-free implementation using both, the power iteration method and the Krylov-Schur method. The performance of these methods has been compared solving different benchmark problems with different dominant ratios.
机译:已经开发出离散纵坐标方法来近似中子输运方程,以计算给定配置的核反应堆堆芯的λ模式。该方法基于离散坐标法进行角度离散化,从而导致非常大且稀疏的代数广义特征值问题。该问题的主导特征值及其对应的特征函数的计算已通过使用幂迭代方法和Krylov-Schur方法两者的无矩阵实现来完成。已经比较了这些方法的性能,以不同的主导比率解决了不同的基准问题。

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