An analytic solution for the critical, monoenergetic, bare, infinite cylinder is presented. The solution is obtained by modifying a previous development based on a neutron density transform and Case's singular eigenfunction method. Numerical results for critical radii and the neutron density as a function of position are included and compared with the results of other methods
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
A method is presented for determining the critical size of a cylindrical reactor by a one-dimensiona...
The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal me...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
The convergence of the approximate method, referred to as An, to study the solution of the monokinet...
Solution of initial value problem in linear transport theory obtained by monoenergetic neutrons migr...
The objective of this paper is to give a mathematical framework for a fully discrete numerical appro...
Typescript (photocopy).An approximate solution method has been developed to solve the one-dimensiona...
The objective of this paper is to give a mathematical framework for a fully discrete numerical appro...
A standard procedure for the solution of singular integral equations is applied to the one-dimension...
Time dependent monoenergetic neutron transport in finite slab with finite reflector
An investigation is made of the usefulness of a variational method for the calculation of the neutro...
In the present work is determined the analytical solution to the neutron transport equation in two-...
An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotr...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
A method is presented for determining the critical size of a cylindrical reactor by a one-dimensiona...
The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal me...
The normal mode expansion technique is applied to the transformed monoenergetic integral transport e...
Transport solutions to the monoenergetic plane, spherical, and cylindrical critical problems with is...
The convergence of the approximate method, referred to as An, to study the solution of the monokinet...
Solution of initial value problem in linear transport theory obtained by monoenergetic neutrons migr...
The objective of this paper is to give a mathematical framework for a fully discrete numerical appro...
Typescript (photocopy).An approximate solution method has been developed to solve the one-dimensiona...
The objective of this paper is to give a mathematical framework for a fully discrete numerical appro...
A standard procedure for the solution of singular integral equations is applied to the one-dimension...
Time dependent monoenergetic neutron transport in finite slab with finite reflector
An investigation is made of the usefulness of a variational method for the calculation of the neutro...
In the present work is determined the analytical solution to the neutron transport equation in two-...
An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotr...
The monoenergetic steady-state integral neutron transport equation is solved analytically for severa...
A method is presented for determining the critical size of a cylindrical reactor by a one-dimensiona...
The usual strategy for solving the neutron diffusion equation in two or three dimensions by nodal me...