An algorithm for decomposing tally data in Monte Carlo simulations using servers has recently been proposed and analyzed. In the present work, we make a number of refinements to a theoretical performance model of the tally server algorithm to better predict the performance of a realistic reactor simulation using Monte Carlo. The impact of subdividing fuel into annular segments on parameters of the performance model is evaluated and shown to result in a predicted overhead of less than 20% for a PWR benchmark on the Mira Blue Gene/Q supercomputer. Additionally, a parameter space study is performed comparing tally server implementations using blocking and non-blocking communication. Non-blocking communication is shown to reduce the communicati...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
As technical support of the French Nuclear Safety Authority, IRSN has been developing the MORET Mont...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
An algorithm for decomposing tally data in Monte Carlo simulations using servers has recently been p...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Abstract: In Monte Carlo (MC) criticality simulation, fission neutrons accumulated in a generation n...
The traditional form of parallelism in Monte Carlo particle transport simulations, wherein each indi...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
A model is developed to predict the impact of particle load imbalances on the performance of domain-...
The number of applications of the Monte Carlo method augmented with the increase of computers speed ...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
AbstractBuilding a new generation of fission reactors in the United States presents many technical a...
This electronic version was submitted by the student author. The certified thesis is available in th...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
As technical support of the French Nuclear Safety Authority, IRSN has been developing the MORET Mont...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
An algorithm for decomposing tally data in Monte Carlo simulations using servers has recently been p...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
Abstract: In Monte Carlo (MC) criticality simulation, fission neutrons accumulated in a generation n...
The traditional form of parallelism in Monte Carlo particle transport simulations, wherein each indi...
The applications of Monte Carlo method in reactor physics analysis is somewhat restricted due to exc...
A model is developed to predict the impact of particle load imbalances on the performance of domain-...
The number of applications of the Monte Carlo method augmented with the increase of computers speed ...
A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan Nation...
In this work we describe a new method for parallelizing the source iterations in a Monte Carlo criti...
AbstractBuilding a new generation of fission reactors in the United States presents many technical a...
This electronic version was submitted by the student author. The certified thesis is available in th...
Monte Carlo (MC) neutral particle transport codes are considered the gold-standard for nuclear simul...
As technical support of the French Nuclear Safety Authority, IRSN has been developing the MORET Mont...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...