summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying medium is discussed provided the initial distribution is known. The macroscopic effective cross-sections and sources are considered to be functions of spatial, angular, energetic and time coordinates. Two theorems asserting the existence and uniqueness of the solution of the problem are presented
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or pho...
AbstractThe purpose of this paper is to investigate a class of time-dependent neutron transport equa...
A standard procedure for the solution of singular integral equations is applied to the one-dimension...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
summary:Transport equation for the function of the neutron density in a non-multiplying medium is di...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
Abstract: The different physical processes of neutron transport are considered in the case...
SIGLEAvailable from British Library Document Supply Centre- DSC:9106.17(CUED/A-NUCL/TR--3) / BLDSC -...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
In this paper, whose purpose is pedagogic, we discuss some distinctive features of neutron transport...
The solution of the linear transport equation used for the study of neutral particle fields requires...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
The solution to the one-energy-group diffusion equation for the case of a point neutron source on th...
A new method of treating problems involving the transport equation is dis-cussed. Starting from Van ...
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or pho...
AbstractThe purpose of this paper is to investigate a class of time-dependent neutron transport equa...
A standard procedure for the solution of singular integral equations is applied to the one-dimension...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
summary:Transport equation for the function of the neutron density in a non-multiplying medium is di...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
Abstract: The different physical processes of neutron transport are considered in the case...
SIGLEAvailable from British Library Document Supply Centre- DSC:9106.17(CUED/A-NUCL/TR--3) / BLDSC -...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
In this paper, whose purpose is pedagogic, we discuss some distinctive features of neutron transport...
The solution of the linear transport equation used for the study of neutral particle fields requires...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
The solution to the one-energy-group diffusion equation for the case of a point neutron source on th...
A new method of treating problems involving the transport equation is dis-cussed. Starting from Van ...
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or pho...
AbstractThe purpose of this paper is to investigate a class of time-dependent neutron transport equa...
A standard procedure for the solution of singular integral equations is applied to the one-dimension...
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