A robust multivariate time series method has been established for the Monte Carlo calculation of neutron multiplication problems. The method is termed Coarse Mesh Projection Method (CMPM) and can be implemented using the coarse statistical bins for acquisition of nuclear fission source data. A novel aspect of CMPM is the combination of the general technical principle of projection pursuit in the signal processing discipline and the neutron multiplication eigenvalue problem in the nuclear engineering discipline. CMPM enables reactor physicists to accurately evaluate major eigenvalue separations of nuclear reactors with continuous energy Monte Carlo calculation. CMPM was incorporated in the MCNP Monte Carlo particle transport code of Los Alam...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
The safe and reliable operation of a nuclear power plant requires a meticulous understanding of the ...
A new Monte Carlo (MC) eigenvalue calculation scheme that substantially reduces the number of cycles...
An efficient Monte Carlo (MC) eigenvalue calculation method for source convergence acceleration and ...
This dissertation develops methods to make time-dependent Monte Carlo transport calculations for rea...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
The Monte Carlo method for solving reactor physics problems is one of the most robust numerical tech...
A Monte Carlo implementation of explicitly restarted Arnoldi’s method is developed for estimating ei...
This thesis investigates Monte Carlo methods applied to criticality and time-dependent problems in r...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
The thesis focuses on the development of high accuracy Monte Carlo-thermal hydraulics Multiphysics m...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
The safe and reliable operation of a nuclear power plant requires a meticulous understanding of the ...
A new Monte Carlo (MC) eigenvalue calculation scheme that substantially reduces the number of cycles...
An efficient Monte Carlo (MC) eigenvalue calculation method for source convergence acceleration and ...
This dissertation develops methods to make time-dependent Monte Carlo transport calculations for rea...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
The Monte Carlo method for solving reactor physics problems is one of the most robust numerical tech...
A Monte Carlo implementation of explicitly restarted Arnoldi’s method is developed for estimating ei...
This thesis investigates Monte Carlo methods applied to criticality and time-dependent problems in r...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
The thesis focuses on the development of high accuracy Monte Carlo-thermal hydraulics Multiphysics m...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [...