In July of 1999 Louisiana State University (LSU) was awarded a two year research grant by the D.O.E. NEER program to develop a methodology for neutron transport calculations using pointwise (PW) nuclear data in the thermal energy range, and to implement the method into the CENTRM transport code being developed at LSU for Oak Ridge National Laboratory (ORNL). This work has extended CENTRM's current epithermal PW calculation to encompass the thermal range, providing a continuous-energy deterministic transport code that can address problems that may not be adequately treated using multigroup methods. The new version of the CENTRM code was completed, and provided to ORNL for inclusion in the next release of the SCALE code system. The new therma...
Transport of low energy neutrons associated with the galactic cosmic ray cascade is analyzed in this...
Because of the requirement of accountability and quality control in the scientific world, a demand f...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...
The purpose of this study is to develop a new method to compute a continuous-energy representation o...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
We present significant improvements and validations of a deterministic neutron transport code (NEUTR...
Consulta en la Biblioteca ETSI Industriales (9055)[EN] The rapid development of computer systems and...
The work performed in this project consisted of the derivation, implementation, and testing of a new...
THERMAL is designed to calculate neutron thermal scattering that is elastic and isotropic in the cen...
Convenient access to accurate nuclear data, particularly data describing low-energy neutrons, is cru...
A neutron transport algorithm including both elastic and nonelastic particle interaction processes f...
Nuclear reactors are complex, coupled, multi-physics and multi-scale systems. There are usually two ...
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigate...
Abstract: Problem statement: In this study, we present general analytical solutions to the Neutron B...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
Transport of low energy neutrons associated with the galactic cosmic ray cascade is analyzed in this...
Because of the requirement of accountability and quality control in the scientific world, a demand f...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...
The purpose of this study is to develop a new method to compute a continuous-energy representation o...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
We present significant improvements and validations of a deterministic neutron transport code (NEUTR...
Consulta en la Biblioteca ETSI Industriales (9055)[EN] The rapid development of computer systems and...
The work performed in this project consisted of the derivation, implementation, and testing of a new...
THERMAL is designed to calculate neutron thermal scattering that is elastic and isotropic in the cen...
Convenient access to accurate nuclear data, particularly data describing low-energy neutrons, is cru...
A neutron transport algorithm including both elastic and nonelastic particle interaction processes f...
Nuclear reactors are complex, coupled, multi-physics and multi-scale systems. There are usually two ...
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigate...
Abstract: Problem statement: In this study, we present general analytical solutions to the Neutron B...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
Transport of low energy neutrons associated with the galactic cosmic ray cascade is analyzed in this...
Because of the requirement of accountability and quality control in the scientific world, a demand f...
The Numerical Nuclear Reactor (NNR) is a code suite that is being developed to provide high-fidelity...