Numerical Computation of Eigenvalue for Steady Neutron Transport Equation

HONG Zhenying; YUAN Guangwei; FU Xuedong

Mar. 2025

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HONG Zhenying, YUAN Guangwei, FU Xuedong. Numerical Computation of Eigenvalue for Steady Neutron Transport Equation[J]. Nuclear Power Engineering, 2012, 33(3): 6-11.

Citation:

HONG Zhenying, YUAN Guangwei, FU Xuedong. Numerical Computation of Eigenvalue for Steady Neutron Transport Equation[J]. Nuclear Power Engineering, 2012, 33(3): 6-11.

HONG Zhenying, YUAN Guangwei, FU Xuedong. Numerical Computation of Eigenvalue for Steady Neutron Transport Equation[J]. Nuclear Power Engineering, 2012, 33(3): 6-11.

Citation:

HONG Zhenying, YUAN Guangwei, FU Xuedong. Numerical Computation of Eigenvalue for Steady Neutron Transport Equation[J]. Nuclear Power Engineering, 2012, 33(3): 6-11.

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Numerical Computation of Eigenvalue for Steady Neutron Transport Equation

Institute of Applied Physics and Computational Mathematics, Beijing, 100094, China

Received Date: 2011-03-24
Rev Recd Date: 2011-12-23

Available Online: 2025-03-08

Abstract

Abstract

The iteration progress will not succeed in the computation of eigenvalue for the neutron transport equations,when considering more expanding number for anisotropic scattering source or more discrete direction for discrete ordinate method.In this paper,the numerical computation of eigenvalue is studied for spherical steady neutron transport equation and a new method is constructed.The new method can improve the convergence rate and nonconvergent case.The modification of computation for k_eff eigenvalue will not dependent on the iterative initial value and the numerical results are stable.
- α eigenvalue,
- k_eff eigenvalue,
- Discrete ordinate,
- Anisotropic scattering source