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- Title
S<sub>4</sub> Solution of the Transport Equation for Eigenvalues: Isotropic, Forward and Backward Scattering in a Slab.
- Authors
ÖZTÜRK, Hakan
- Abstract
The neutron transport equation is solved numerically for monoenergetic neutrons in a finite homogeneous slab with backward and forward scattering for the eigenvalue spectrum. The forward-backward-isotropic (FBI) scattering kernel is chosen for representing the neutron scattering in transport equation. Then, the transport equation is converted into a discrete ordinates form by using the integral transform technique with the even-order Gauss-Legendre quadrature set. Finally, the eigenvalues are calculated for a medium from weakly absorbing to highly scattering condition using various values of the scattering, backward and forward scattering parameters. Gauss-Legendre quadrature sets are used for all calculations and the calculated eigenvalues are given in the tables.
- Subjects
NEUTRON transport theory; INVERSE scattering transform; EIGENVALUE equations; HYPERGEOMETRIC functions; MONOENERGETIC radiation; FINITE difference method
- Publication
Suleyman Demirel University Faculty of Arts & Science Journal of Science / Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi, 2017, Vol 12, Issue 2, p1
- ISSN
1306-7575
- Publication type
Article