AbstractThe steady-state equation for N-group neutron transport in slab geometry is written as an integral equation. A spectral analysis is made of the integral operator and related to the criticality problem. The method depends on a representation for the resolvent kernel for a subcritical slab and on analytic continuation in a complex parameter to characterize eigenvalues in terms of singularities of the resolvent. The analytic continuation is based on a bifurcation analysis of some nonlinear matrix integral equations whose solutions provide a matrix Wiener-Hopf factorization of the Fourier transform of the kernel of the transport operator
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transpor...
This dissertation is mainly devoted to spectral analysis of various neutron transport models. It is ...
AbstractThe steady-state equation for N-group neutron transport in slab geometry is written as an in...
AbstractIn this paper, we consider the criticality problem for energy dependent neutron transport in...
AbstractThe steady-state equation for energy-dependent neutron transport in isotropically scattering...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
We address the homogenization of an eigenvalue problem for the neutron transport equation in a per...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
A new formulation of the density eigenvalue problem for the neutron transport equation is pre- sente...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
Many groups of researchers have calculated the spectrum of the transport equation in different geome...
One speed, time independent neutron transport equation in slab geometry can be solved with the tripl...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
The integral form of the one-speed, steady-state Boltzmann transport equation is solved for a point ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transpor...
This dissertation is mainly devoted to spectral analysis of various neutron transport models. It is ...
AbstractThe steady-state equation for N-group neutron transport in slab geometry is written as an in...
AbstractIn this paper, we consider the criticality problem for energy dependent neutron transport in...
AbstractThe steady-state equation for energy-dependent neutron transport in isotropically scattering...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
We address the homogenization of an eigenvalue problem for the neutron transport equation in a per...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
A new formulation of the density eigenvalue problem for the neutron transport equation is pre- sente...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
Many groups of researchers have calculated the spectrum of the transport equation in different geome...
One speed, time independent neutron transport equation in slab geometry can be solved with the tripl...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
The integral form of the one-speed, steady-state Boltzmann transport equation is solved for a point ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transpor...
This dissertation is mainly devoted to spectral analysis of various neutron transport models. It is ...