The feasibility and practical implementation of axial expansion methods for the solution of the multi-dimensional multigroup neutron diffusion (MGD) equations is investigated. The theoretical examination which is applicable to the general MGD equations in arbitrary geometry includes the derivation of a new weak (reduced) form of the MGD equations by exp and ing the axial component of the neutron flux in a series of known trial functions and utilizing the Galerkin weighting. A general two-group albedo boundary condition is included in the weak form as a natural boundary condition. The application of different types of trial functions is presented. The practical implementation of the axial expansion method has involved two major tasks: (1) th...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
Several polynomial finite elements of nodal type are introduced that should lead to convergence of O...
Designing and analyzing nuclear reactors requires the development of software tools for the simulati...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
172 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The multigroup neutron diffus...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
Vita.Angular singularities for the multigroup neutron diffusion equation are examined. Since the sol...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Nucl.E.Leaf [174]...
Recently a solver based on the Method Of Characteristics (MOC) for 3D extruded geometries has been d...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, n...
The nodal methods are significantly more accurate than the traditional methods such as finite differ...
The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylind...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
Several polynomial finite elements of nodal type are introduced that should lead to convergence of O...
Designing and analyzing nuclear reactors requires the development of software tools for the simulati...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
172 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The multigroup neutron diffus...
In this work we present a methodology of solution of the multigroup multi-layer stationary neutron d...
Vita.Angular singularities for the multigroup neutron diffusion equation are examined. Since the sol...
Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Nucl.E.Leaf [174]...
Recently a solver based on the Method Of Characteristics (MOC) for 3D extruded geometries has been d...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, n...
The nodal methods are significantly more accurate than the traditional methods such as finite differ...
The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylind...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
A method, called the higher mode synthesis method, for the solution of the two-dimensional neutron d...
Several polynomial finite elements of nodal type are introduced that should lead to convergence of O...