The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solver that provides transport solutions to heterogeneous reactor cores. In this paper, COMET is tested against continuous energy Monte Carlo in solving the recently developed stylized Small Modular Advanced High-Temperature Reactor (SmAHTR) Benchmark Problems based on the Oak Ridge National Laboratory pre-conceptual design (core configurations). These problems are well-suited to test the performance of advanced neutronics tools because of their unique neutronics characteristics such as the multiple heterogeneities. The COMET solutions for the three benchmark problems were found to agree very well with the continuous energy Monte Carlo reference s...
This thesis presents a formulation for an adaptive COMET method for solving whole reactor eigenvalue...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solve...
In recent years, there has been much improvement in radiation therapy delivery systems used in the t...
This thesis presents a whole-core benchmark of the European Pressurized Reactor (EPR) using multipl...
This work developed a stylized three dimensional benchmark problem based on Argonne National Laborat...
The Coarse Mesh Radiation Transport (COMET) method is a reactor physics method and code that has bee...
Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has ...
This paper presents the application and evaluation of a deterministic truncation of Monte Carlo (DTM...
The Continuous-Energy Coarse Mesh Transport (COMET) method is a neutron transport solution method th...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
textAmong the most formidable challenges facing our world is the need for safe, clean, affordable en...
This paper presents a new hybrid method of continuous energy Monte Carlo (MC) and multi-group Method...
This thesis presents a formulation for an adaptive COMET method for solving whole reactor eigenvalue...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...
The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solve...
In recent years, there has been much improvement in radiation therapy delivery systems used in the t...
This thesis presents a whole-core benchmark of the European Pressurized Reactor (EPR) using multipl...
This work developed a stylized three dimensional benchmark problem based on Argonne National Laborat...
The Coarse Mesh Radiation Transport (COMET) method is a reactor physics method and code that has bee...
Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has ...
This paper presents the application and evaluation of a deterministic truncation of Monte Carlo (DTM...
The Continuous-Energy Coarse Mesh Transport (COMET) method is a neutron transport solution method th...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
textAmong the most formidable challenges facing our world is the need for safe, clean, affordable en...
This paper presents a new hybrid method of continuous energy Monte Carlo (MC) and multi-group Method...
This thesis presents a formulation for an adaptive COMET method for solving whole reactor eigenvalue...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
A considerable speed-up in continuous-energy Monte Carlo neutron transport calculation can be achiev...