Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simulations, but they cannot be robustly applied to high-fidelity nuclear reactor analysis without accommodating several terabytes of materials and tally data. While this is not a large amount of aggregate data for a typical high performance computer, MC methods are only embarrassingly parallel when the key data structures are replicated for each processing element, an approach which is likely infeasible on future machines. The present work explores the use of spatial domain decomposition to make full-scale nuclear reactor simulations tractable with Monte Carlo methods, presenting a simple implementation in a production-scale code. Good performanc...
The NEA Monte Carlo Performance benchmark started in 2011 aiming to monitor over the years the abili...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
AbstractBecause of prohibitive data storage requirements in large-scale simulations, the memory prob...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
An algorithm for decomposing tally data in Monte Carlo simulations using servers has recently been p...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
In this study we present and analyze a formulation of the 3D Method of Characteristics (MOC) techniq...
To examine the domain decomposition code coupled Monte Carlo-finite element calculation, it is impor...
The safe and reliable operation of a nuclear power plant requires a meticulous understanding of the ...
The NEA Monte Carlo Performance benchmark started in 2011 aiming to monitor over the years the abili...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
AbstractBecause of prohibitive data storage requirements in large-scale simulations, the memory prob...
Monte Carlo neutron transport codes are a growing subject of research in nuclear reactor analysis. F...
An algorithm for decomposing tally data in Monte Carlo simulations using servers has recently been p...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
In this study we present and analyze a formulation of the 3D Method of Characteristics (MOC) techniq...
To examine the domain decomposition code coupled Monte Carlo-finite element calculation, it is impor...
The safe and reliable operation of a nuclear power plant requires a meticulous understanding of the ...
The NEA Monte Carlo Performance benchmark started in 2011 aiming to monitor over the years the abili...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...