The computer code block VENTURE, designed to solve multigroup neutronics problems with application of the finite-difference diffusion-theory approximation to neutron transport (or alternatively simple P$sub 1$) in up to three- dimensional geometry is described. A variety of types of problems may be solved: the usual eigenvalue problem, a direct criticality search on the buckling, on a reciprocal velocity absorber (prompt mode), or on nuclide concentrations, or an indirect criticality search on nuclide concentrations, or on dimensions. First- order perturbation analysis capability is available at the macroscopic cross section level. (auth
The feasibility and practical implementation of axial expansion methods for the solution of the mult...
Finite difference techniques are used to solve a variety of differential equations. For the neutron ...
DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity...
The report documents the computer code block VENTURE designed to solve multigroup neutronics problem...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
The objectives of the work are to develop mathematically and computationally founded for the design ...
International audienceThe Laboratory for Reactor Physics and Systems Behaviour at the PSI and the EP...
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, n...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffu...
The mathematical and computational structure of POW3D, a general purpose zero, one, two and three-di...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensi...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The feasibility and practical implementation of axial expansion methods for the solution of the mult...
Finite difference techniques are used to solve a variety of differential equations. For the neutron ...
DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity...
The report documents the computer code block VENTURE designed to solve multigroup neutronics problem...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
The objectives of the work are to develop mathematically and computationally founded for the design ...
International audienceThe Laboratory for Reactor Physics and Systems Behaviour at the PSI and the EP...
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, n...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffu...
The mathematical and computational structure of POW3D, a general purpose zero, one, two and three-di...
A neutronic module for the solution of two-dimensional steady-state multigroup diffusion problems in...
Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensi...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The feasibility and practical implementation of axial expansion methods for the solution of the mult...
Finite difference techniques are used to solve a variety of differential equations. For the neutron ...
DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity...