S₄ solution of the transport equation for eigenvalues using Legendre polynomials

Abstract

Abstract. Numerical solution of the transport equation for monoenergetic neutrons scattered isotropically through the medium of a finite homogeneous slab is studied for the determination of the eigenvalues. After obtaining the discrete ordinates form of the transport equation, separated homogeneous and particular solutions are formed and then the eigenvalues are calculated using the Gauss-Legendre quadrature set. Then, the calculated eigenvalues for various values of the c 0 , the mean number of secondary neutrons per collision, are given in the tables.