This project has resulted in a highly efficient method that has been shown to provide accurate solutions to a variety of 2D and 3D reactor problems. The goal of this project was to develop (1) an accurate and efficient three-dimensional whole-core neutronics method with the following features: based sollely on transport theory, does not require the use of cross-section homogenization, contains a highly accurate and self-consistent global flux reconstruction procedure, and is applicable to large, heterogeneous reactor models, and to (2) create new numerical benchmark problems for code cross-comparison
Most modern nodal methods in use by the reactor vendors and utilities are based on the generalized e...
International audienceWe present in this paper a discrete-ordinates transport method to perform 3D P...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
Current advancements in nuclear reactor core design are pushing reactor cores towards greater hetero...
A new three-dimensional (3D) transport analysis method is developed and implemented in the light wat...
A new interactive homogenization procedure for reactor core or colorset calculations is proposed tha...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A heterogeneous coarse mesh scheme based on the finite element response matrix has been developed an...
The superior advantage of a nodal method for reactor cores with hexagonal fuel assemblies discretize...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety an...
Three-dimensional deterministic core calculations are typically based on the classical two-step appr...
A Variational Transport Theory Method for Two-Dimensional Reactor Core Calculations Scott W. Mos...
International audienceFast resolution of the Boltzmann transport equation over a nuclear reactor cor...
Most modern nodal methods in use by the reactor vendors and utilities are based on the generalized e...
International audienceWe present in this paper a discrete-ordinates transport method to perform 3D P...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
Current advancements in nuclear reactor core design are pushing reactor cores towards greater hetero...
A new three-dimensional (3D) transport analysis method is developed and implemented in the light wat...
A new interactive homogenization procedure for reactor core or colorset calculations is proposed tha...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
A heterogeneous coarse mesh scheme based on the finite element response matrix has been developed an...
The superior advantage of a nodal method for reactor cores with hexagonal fuel assemblies discretize...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety an...
Three-dimensional deterministic core calculations are typically based on the classical two-step appr...
A Variational Transport Theory Method for Two-Dimensional Reactor Core Calculations Scott W. Mos...
International audienceFast resolution of the Boltzmann transport equation over a nuclear reactor cor...
Most modern nodal methods in use by the reactor vendors and utilities are based on the generalized e...
International audienceWe present in this paper a discrete-ordinates transport method to perform 3D P...
summary:We present a method for solving the equations of neutron transport with discretized energeti...