An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotropic burst of neutrons introduced at the interface separating two adjacent, dissimilar, semi-infinite media. The method of solution used is to remove the time dependence by a Laplace transformation, solve the transformed equation by the normal mode expansion method, and then invert to recover the time dependence. The general result is expressed as a sum of definite, multiple integrals, one of which contains the uncollided wave of neutrons originating at the source plane. It is possible to obtain a simplified form for the solution at the interface, and certain numerical calculations are made there. The interface flux in two adja...
Abstract-- The time-dependent neutron transport problem is approximated using the Pomraning-Eddingto...
The method developed by Case is used to solve four time‐independent, one‐speed problems for neutron ...
Mathematical model for neutron diffusion mechanics in heterogeneous media with vacuum channel
Time dependent monoenergetic neutron transport in finite slab with finite reflector
A Laplace transformation technique is used to determine the neutron distribution in a semi‐infinite ...
Solution of initial value problem in linear transport theory obtained by monoenergetic neutrons migr...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
We have derived from the Boltzmann equation a new integral equation governing the slowing down of ne...
This item was digitized from a paper original and/or a microfilm copy. If you need higher-resolution...
The pulsed neutron technique has been used to investigate the decay of thermal neutrons in two adjac...
Using Case's method for solving the one‐speed transport equation with isotropic scattering, the Miln...
summary:This paper concerns $l$-velocity model of the general linear time-dependent transport equati...
Aspects of the problem of neutron slowing down and transport in an infinite medium consisting of a s...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Abstract-- The time-dependent neutron transport problem is approximated using the Pomraning-Eddingto...
The method developed by Case is used to solve four time‐independent, one‐speed problems for neutron ...
Mathematical model for neutron diffusion mechanics in heterogeneous media with vacuum channel
Time dependent monoenergetic neutron transport in finite slab with finite reflector
A Laplace transformation technique is used to determine the neutron distribution in a semi‐infinite ...
Solution of initial value problem in linear transport theory obtained by monoenergetic neutrons migr...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
We have derived from the Boltzmann equation a new integral equation governing the slowing down of ne...
This item was digitized from a paper original and/or a microfilm copy. If you need higher-resolution...
The pulsed neutron technique has been used to investigate the decay of thermal neutrons in two adjac...
Using Case's method for solving the one‐speed transport equation with isotropic scattering, the Miln...
summary:This paper concerns $l$-velocity model of the general linear time-dependent transport equati...
Aspects of the problem of neutron slowing down and transport in an infinite medium consisting of a s...
summary:In this paper, the initial-value problem, the problem of asymptotic time behaviour of its so...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Abstract-- The time-dependent neutron transport problem is approximated using the Pomraning-Eddingto...
The method developed by Case is used to solve four time‐independent, one‐speed problems for neutron ...
Mathematical model for neutron diffusion mechanics in heterogeneous media with vacuum channel