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 theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
We study a class of nonlinear equations arising in the stochastic theory of neutron transport. After...
A Laplace transformation technique is used to determine the neutron distribution in a semi‐infinite ...
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...
In an attempt to understand the conditions under which the neutron transport equation has solutions,...
AbstractThe purpose of this paper is to investigate a class of time-dependent neutron transport equa...
Aspects of the problem of neutron slowing down and transport in an infinite medium consisting of a s...
A new method of treating problems involving the transport equation is discussed. Starting from Van K...
summary:In this paper, the initial value problem for the equations of reactor kinetics is solved and...
summary:This paper concerns $l$-velocity model of the general linear time-dependent transport equati...
Dept. of Mathematics and Statistics. Paper copy at Leddy Library: Theses & Major Papers - Basement, ...
Integro-differential equation describing the diffusion of neutrons in a multiplying medium is studie...
An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotr...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
We study a class of nonlinear equations arising in the stochastic theory of neutron transport. After...
A Laplace transformation technique is used to determine the neutron distribution in a semi‐infinite ...
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...
In an attempt to understand the conditions under which the neutron transport equation has solutions,...
AbstractThe purpose of this paper is to investigate a class of time-dependent neutron transport equa...
Aspects of the problem of neutron slowing down and transport in an infinite medium consisting of a s...
A new method of treating problems involving the transport equation is discussed. Starting from Van K...
summary:In this paper, the initial value problem for the equations of reactor kinetics is solved and...
summary:This paper concerns $l$-velocity model of the general linear time-dependent transport equati...
Dept. of Mathematics and Statistics. Paper copy at Leddy Library: Theses & Major Papers - Basement, ...
Integro-differential equation describing the diffusion of neutrons in a multiplying medium is studie...
An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotr...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
We study a class of nonlinear equations arising in the stochastic theory of neutron transport. After...
A Laplace transformation technique is used to determine the neutron distribution in a semi‐infinite ...
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