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Multilevel NDA Methods for Solving Multigroup Eigenvalue Neutron Transport Problems

Dmitriy Y. Anistratov

Nuclear Science and Engineering / Volume 174 / Number 2 / Pages 150-162

June 2013

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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.

 
 
 
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