In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criticality calculation. Instead of having one global fission bank that needs to be synchronized, as is traditionally done, our method has each processor keep track of a local fission bank while still preserving reproducibility. In doing so, it is required to send only a limited set of fission bank sites between processors, thereby drastically reducing the total amount of data sent through the network. The algorithm was implemented in a simple Monte Carlo code and shown to scale up to hundreds of processors and furthermore outperforms traditional algorithms by at least two orders of magnitude in wall-clock time
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
This thesis presents a compilation of work focused on Monte Carlo crit-icality, kinetics and burnup ...
Fission source convergence in Monte Carlo criticality calculations can be difficult for some types o...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Criticality calculations use the source iteration method and serve an increasingly prominent role in...
Abstract: In Monte Carlo (MC) criticality simulation, fission neutrons accumulated in a generation n...
We compare nominal efficiencies, i.e. variances in power shapes for equal running time, of different...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
This paper presents strategies to parallelize a previously implemented kinetic Monte Carlo (kMC) alg...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a...
This dissertation develops methods to make time-dependent Monte Carlo transport calculations for rea...
Abstract. We argue that Monte Carlo algorithms are ideally suited to parallel computing, and that “p...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
This thesis presents a compilation of work focused on Monte Carlo crit-icality, kinetics and burnup ...
Fission source convergence in Monte Carlo criticality calculations can be difficult for some types o...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Criticality calculations use the source iteration method and serve an increasingly prominent role in...
Abstract: In Monte Carlo (MC) criticality simulation, fission neutrons accumulated in a generation n...
We compare nominal efficiencies, i.e. variances in power shapes for equal running time, of different...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
This paper presents strategies to parallelize a previously implemented kinetic Monte Carlo (kMC) alg...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a...
This dissertation develops methods to make time-dependent Monte Carlo transport calculations for rea...
Abstract. We argue that Monte Carlo algorithms are ideally suited to parallel computing, and that “p...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
This thesis presents a compilation of work focused on Monte Carlo crit-icality, kinetics and burnup ...
Fission source convergence in Monte Carlo criticality calculations can be difficult for some types o...