A new method for computing homogenized assembly neutron transport cross sections and diffusion coefficients that is both rigorous and computationally efficient is proposed in this paper. In the limit of a homogeneous hydrogen slab, the new method is equivalent to the long-used, and only-recently-published CASMO transport method. The rigorous method is used to demonstrate the sources of inaccuracy in the commonly applied “out-scatter” transport correction. It is also demonstrated that the newly developed method is directly applicable to lattice calculations performed by Monte Carlo and is capable of computing rigorous homogenized transport cross sections for arbitrarily heterogeneous lattices. Comparisons of several common transport cross ...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
For practical reactor core applications low-order transport approximations such as SP3 have been sho...
Many applications in reactor physics still use the diffusion equation on a full reactor core with ho...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutro...
Neutron transport calculations by Monte Carlo methods are finding increased application in nuclear r...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR),...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
The generation of multigroup neutron cross sections is usually the first step in the solution of rea...
In Very High Temperature Reactors (VHTRs), the long mean-free-path and large migration area of neutr...
International audienceFast resolution of the Boltzmann transport equation over a nuclear reactor cor...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
For practical reactor core applications low-order transport approximations such as SP3 have been sho...
Many applications in reactor physics still use the diffusion equation on a full reactor core with ho...
Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditi...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutro...
Neutron transport calculations by Monte Carlo methods are finding increased application in nuclear r...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR),...
This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended f...
The generation of multigroup neutron cross sections is usually the first step in the solution of rea...
In Very High Temperature Reactors (VHTRs), the long mean-free-path and large migration area of neutr...
International audienceFast resolution of the Boltzmann transport equation over a nuclear reactor cor...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
For practical reactor core applications low-order transport approximations such as SP3 have been sho...