AbstractIn this paper, we consider the criticality problem for energy dependent neutron transport in an isotropically scattering, homogeneous slab. Under a positivity assumption on the scattering kernel, we can find an expression relating the thickness of the slab to a parameter characterizing production by fission. This is accomplished by exploiting the Perron-Frobenius-Jentsch characterization of positive operators (i.e. those leaving invariant a normal, reproducing cone in a Banach space). We point out that those techniques work for classes of multigroup problems where the Case singular eigenfunction approach is not as feasible as in the one-group theory, which is also analyzed
We address the homogenization of an eigenvalue problem for the neutron transport equation in a per...
The one speed, time independent neutron transport equation for slab geometry with quadratic anisotro...
Tureci, RG/0000-0001-6309-6300WOS: 000368672700011One speed, time independent neutron transport equa...
AbstractThe steady-state equation for energy-dependent neutron transport in isotropically scattering...
AbstractThe steady-state equation for N-group neutron transport in slab geometry is written as an in...
The criticality problem is studied based on one-speed time-dependent neutron transport theory, for a...
WOS: 000266185400005The criticality problem is studied based on one-speed time-dependent neutron tra...
One speed, time independent neutron transport equation in slab geometry can be solved with the tripl...
Integro-differential equation describing the diffusion of neutrons in a multiplying medium is studie...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
A new formulation of the density eigenvalue problem for the neutron transport equation is pre- sente...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
The space asymptotic theory has constituted a powerful tool for the determination of neutron energy ...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
The UN method is used to solve the critical slab problem for reflecting boundary conditions in one-s...
We address the homogenization of an eigenvalue problem for the neutron transport equation in a per...
The one speed, time independent neutron transport equation for slab geometry with quadratic anisotro...
Tureci, RG/0000-0001-6309-6300WOS: 000368672700011One speed, time independent neutron transport equa...
AbstractThe steady-state equation for energy-dependent neutron transport in isotropically scattering...
AbstractThe steady-state equation for N-group neutron transport in slab geometry is written as an in...
The criticality problem is studied based on one-speed time-dependent neutron transport theory, for a...
WOS: 000266185400005The criticality problem is studied based on one-speed time-dependent neutron tra...
One speed, time independent neutron transport equation in slab geometry can be solved with the tripl...
Integro-differential equation describing the diffusion of neutrons in a multiplying medium is studie...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
A new formulation of the density eigenvalue problem for the neutron transport equation is pre- sente...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
The space asymptotic theory has constituted a powerful tool for the determination of neutron energy ...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
The UN method is used to solve the critical slab problem for reflecting boundary conditions in one-s...
We address the homogenization of an eigenvalue problem for the neutron transport equation in a per...
The one speed, time independent neutron transport equation for slab geometry with quadratic anisotro...
Tureci, RG/0000-0001-6309-6300WOS: 000368672700011One speed, time independent neutron transport equa...