Abstract
The emergence of advanced nuclear reactor systems with increasing complexity and heterogeneity has necessitated detailed high fidelity neutronic analysis. This requires exhaustive solution of the neutron transport equation which has the disadvantage of long computation times, especially for scattering dominant problems. In this paper, the performance behavior and stability analysis of several iterative methods for solving the optimally diffusive coarse mesh finite difference (odCMFD) accelerated transport equation has been presented. Efficacy of the acceleration iterations with varying coarse mesh size and convergence criteria of the low order problem, and their overall performance has been investigated for the 2-group LRA-BWR problem and the 7-group C5G7 problem. Prescriptions for different parameters and the most robust iterative scheme have been proposed based on these studies. The theoretical background of odCMFD based acceleration schemes and the numerical results of their application to different problems using the code DIAMOND have been presented in this paper.
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