论文信息 - Multilevel NDA Methods for Solving Multigroup Eigenvalue Neutron Transport Problems

Multilevel NDA Methods for Solving Multigroup Eigenvalue Neutron Transport Problems

Abstract The nonlinear diffusion acceleration (NDA) method is an efficient and flexible transport iterative scheme for solving reactor-physics problems. This paper presents a fast iterative algorithm for solving multigroup neutron transport eigenvalue problems in one-dimensional slab geometry. The proposed method is defined by a multilevel system of equations that includes multigroup and effective one-group low-order NDA equations. The eigenvalue is evaluated in an exact projected solution space of the smallest dimensionality. Numerical results that illustrate the performance of the new algorithm are demonstrated.

Dmitriy Y. Anistratov | Dmitriy Anistratov

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