The theory and application of deterministic, multidimensional, pointwise energy lattice physics methods are discussed. These methods may be used to solve the neutron transport equation in multidimensional geometries using near-continuous energy detail to calculate equivalent few-group diffusion theory constants that rigorously account for spatial and spectral self-shielding effects. A dual energy resolution slowing down algorithm is described which reduces the computer memory and disk storage requirements for the slowing down calculation. Results are presented for a 2D BWR pin cell depletion benchmark problem
Simple expressions for the mean square distance from a point fission source for slowing down past a ...
The objectives of the work are to develop mathematically and computationally founded for the design ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
The theory and application of the RAZOR two-dimensional, continuous energy lattice physics code are ...
In the past twenty 20 years considerable progress has been made in developing new methods for solvin...
Angular approximation techniques to the Boltzmann transport equation have been developed that are ac...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
An experimentation code for deterministic neutron transport in the Sn discretization of the transpor...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
This study addresses the problem of neutron physics calculations in transition regions. Directional ...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
The computer code block VENTURE, designed to solve multigroup neutronics problems with application o...
A Fourier analysis is conducted in two-dimensional (2D) geometry for the discrete-ordinates (SN) app...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
Simple expressions for the mean square distance from a point fission source for slowing down past a ...
The objectives of the work are to develop mathematically and computationally founded for the design ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
The theory and application of the RAZOR two-dimensional, continuous energy lattice physics code are ...
In the past twenty 20 years considerable progress has been made in developing new methods for solvin...
Angular approximation techniques to the Boltzmann transport equation have been developed that are ac...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
An experimentation code for deterministic neutron transport in the Sn discretization of the transpor...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
This study addresses the problem of neutron physics calculations in transition regions. Directional ...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
The computer code block VENTURE, designed to solve multigroup neutronics problems with application o...
A Fourier analysis is conducted in two-dimensional (2D) geometry for the discrete-ordinates (SN) app...
Variational coarse mesh techniques are developed for the solution of the one group neutron transport...
Simple expressions for the mean square distance from a point fission source for slowing down past a ...
The objectives of the work are to develop mathematically and computationally founded for the design ...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...