It has been observed that statistical uncertainties on tallies in Monte Carlo iterated-fission-source calculations tend to be larger for tally regions near reflective boundaries than for similar tally regions far from such boundaries. Using a theoretical methodology developed by Brissenden and Garlick, the cause of this behavior was found to be a greater correlation between fission generations in the regions near the reflective boundaries. The theory was found to be in qualitative agreement with Monte Carlo results for a simple test problem. It is also shown that applying the coarse mesh finite difference method eliminates the anomalous behavior
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
Perturbation techniques are powerful tools for determining the effects of small changes, or perturba...
It has been observed that statistical uncertainties on tallies in Monte Carlo iterated-fission-sourc...
Monte Carlo methods, used to model nuclear systems, have been observed to underpredict the statistic...
In order to accurately estimate uncertainty of fission source distribution in a Monte Carlo calculat...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
International audienceThe behaviour of Monte Carlo criticality simulations is often assessed by exam...
All nuclear decay data have uncertainties. It is not obvious how these uncertainties affect the dete...
The fission source convergence of a very loosely coupled array of 36 fuel subassemblies with slightl...
The recently developed method of fast Total Monte Carlo to propagate nuclear data uncertainties was ...
All nuclear decay data have uncertainties. It is not obvious how these uncertainties affect the dete...
In Monte Carlo (MC) criticality calculations, source error propagation through the stationary cycles...
Temporal correlations arising in Monte Carlo criticality codes have focused the attention of both de...
When applying numerical simulation to physical problems it is important to be able to clearly unders...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
Perturbation techniques are powerful tools for determining the effects of small changes, or perturba...
It has been observed that statistical uncertainties on tallies in Monte Carlo iterated-fission-sourc...
Monte Carlo methods, used to model nuclear systems, have been observed to underpredict the statistic...
In order to accurately estimate uncertainty of fission source distribution in a Monte Carlo calculat...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
International audienceThe behaviour of Monte Carlo criticality simulations is often assessed by exam...
All nuclear decay data have uncertainties. It is not obvious how these uncertainties affect the dete...
The fission source convergence of a very loosely coupled array of 36 fuel subassemblies with slightl...
The recently developed method of fast Total Monte Carlo to propagate nuclear data uncertainties was ...
All nuclear decay data have uncertainties. It is not obvious how these uncertainties affect the dete...
In Monte Carlo (MC) criticality calculations, source error propagation through the stationary cycles...
Temporal correlations arising in Monte Carlo criticality codes have focused the attention of both de...
When applying numerical simulation to physical problems it is important to be able to clearly unders...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
In many reactor calculations, high fidelity, high accuracy results are required only in a small spat...
Perturbation techniques are powerful tools for determining the effects of small changes, or perturba...