Implementation and performance study of lpCMFD acceleration method for multi-energy group k-eigenvalue neutron transport problem in hexagonal geometry
Author:
Funder
National Research Foundation Singapore
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference13 articles.
1. Nodal Method Storage Reduction by Nonlinear Iteration;Smith;Trans. Am. Nucl. Soc.,1983
2. Analysis of Stabilization Techniques for CMFD Acceleration of Neutron Transport Problems;Jarrett;Nucl. Sci. Eng.,2016
3. Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method;Yun;Ann. Nucl. Energy,2010
4. Fourier Convergence Analysis of the Rebalance Methods for Discrete Ordinates Transport Equations in Eigenvalue Problems;Hong;Nucl. Sci. Eng.,2010
5. An optimally diffusive Coarse Mesh Finite Difference method to accelerate neutron transport calculations;Zhu;Ann. Nucl. Energy,2016
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1. lp-CMFD acceleration schemes in multi-energy group 2D Monte Carlo transport;Frontiers in Energy Research;2022-10-19
2. Eigenvalues of the neutron transport equation in X–Y geometry and reflecting boundary conditions;Progress in Nuclear Energy;2022-02
3. Implementation and performance study of the lp-CMFD acceleration scheme for Monte Carlo method based k-eigenvalue neutron transport calculation in 1D geometry;Annals of Nuclear Energy;2021-12
4. A linear prolongation CMFD acceleration for two-dimensional discrete ordinate k-eigenvalue neutron transport calculation with pin-resolved mesh using discontinuous Galerkin finite element method;Annals of Nuclear Energy;2021-05
5. A Linear Prolongating Coarse Mesh Finite Difference Acceleration of Discrete Ordinate Neutron Transport Calculation Based on Discontinuous Galerkin Finite Element Method;Nuclear Science and Engineering;2020-06-12
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