textThe collision probability approach to neutron transport can be used to obtain the energy-dependent neutron spectrum in nuclear reactor systems as well as other quantities of interest. This method makes the approximation that the neutron distribution is constant within homogeneous regions, or cells, in the system. This assumption restricts geometries that can be modeled by the collision probability approach. The geometry modeled is typically an infinite lattice of two homogeneous cells: a fuel pin cylinder and the coolant that surrounds it. The transport of neutrons between the homogeneous cells is done using probabilities describing the chance that a neutron having a collision in one cell has its next collision in another cell. These co...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This document presents the statistical description of neutron cross sections in the unresolved reson...
Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Camp...
Several comprehensive but time consuming neutronic codes are available for performing nuclear reacto...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
The operation of nuclear reactors requires detailed knowledge of important safety parameters, such a...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
A new method for computing homogenized assembly neutron transport cross sections and diffusion coeff...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
In this work we present a scheme for computing temperature-dependent unresolved resonance region cro...
Within this article, current coupling collision probability method with expansion of flux by orthogo...
Simulations for obtaining quantities of interest of neutron transport problems need to be accurate a...
Calculation of burnup of material composing a nuclear reactor is important in a feasibility study of...
Dans le cadre de la conception des réacteurs, les schémas de calculs utilisant des codes de cal- cul...
Neutronics computations are widely used in reactor physics and criticality calculations to ensure th...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This document presents the statistical description of neutron cross sections in the unresolved reson...
Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Camp...
Several comprehensive but time consuming neutronic codes are available for performing nuclear reacto...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
The operation of nuclear reactors requires detailed knowledge of important safety parameters, such a...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
A new method for computing homogenized assembly neutron transport cross sections and diffusion coeff...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
In this work we present a scheme for computing temperature-dependent unresolved resonance region cro...
Within this article, current coupling collision probability method with expansion of flux by orthogo...
Simulations for obtaining quantities of interest of neutron transport problems need to be accurate a...
Calculation of burnup of material composing a nuclear reactor is important in a feasibility study of...
Dans le cadre de la conception des réacteurs, les schémas de calculs utilisant des codes de cal- cul...
Neutronics computations are widely used in reactor physics and criticality calculations to ensure th...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This document presents the statistical description of neutron cross sections in the unresolved reson...
Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Camp...