Browsing Fizik Bölümü Makale Koleksiyonu by Title
Now showing items 20-25 of 25
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S-4 solution of the transport equation for eigenvalues using Legendre polynomials
(EDP SCIENCES., 2017)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 ... -
S4 solution of the transport equation for eigenvalues: isotropic, forward and backward scattering in a slab
(SÜLEYMAN DEMİREL ÜNİV., 2017)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 ... -
Semi-Empirical Formula with New Coefficients of the (alpha,n) Reaction Cross-Section
(POLISH ACAD SCIENCES INST PHYSICS, 2015)A new modified semi-empirical formula including non-elastic scattering and Coulomb effects for the (alpha,n) reaction cross-section was obtained. The available experimental data were used to get the (alpha,n) reaction ... -
Site Identity and Importance in Cosubstituted Bixbyite In2O3
(MDPI., 2017)The bixbyite structure of In2O3 has two nonequivalent, 6-coordinate cation sites and, when Sn is doped into In2O3, the Sn prefers the b-site and produces a highly conductive material. When divalent/tetravalent cation pairs ... -
The eigenvalues of one-speed neutrons in a slab with forward and backward scattering
(UNIV NORTH., 2019)The eigenvalue spectrum is studied for one-speed neutrons in a slab with forward and backward scattering. First, the transport equation describing the interaction of neutrons in a system with general geometry is given. ... -
The influence of linear anisotropic scattering of one-speed neutrons on the critical size of A slab with reflective boundary conditions
(VINCA INST NUCLEAR SCI, 2017)The criticality problem for one-speed neutrons in a slab is investigated using Chebyshev polynomials of first kind in the series expansion of the neutron angular flux in stationary neutron transport equation. The medium ...