In analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simulation. The first step (MC1) simulates neutron transport, and the second step (MC2) transports the decay photons emitted from the activated materials. In this process, the stochastic uncertainty estimated by the MC2 appears only as a final result, but it is underestimated because the stochastic error generated in MC1 cannot be directly included in MC2. Hence, estimating the true stochastic uncertainty requires quantifying the propagation degree of the stochastic error in MC1. The brute force technique is a straightforward method to estimate the true uncertainty. However, it is a costly method to obtain reliable results. Another method, called the adjo...
Uncertainty propagation to keff using a Total Monte Carlo sampling process is commonly used to solve...
Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code w...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
In analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simulation. T...
AbstractIn analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simul...
In activation calculations, there are several approaches to quantify uncertainties: deterministic by...
With the advent of more powerful, less expensive computing resources, more and more attention is bei...
The Monte Carlo (MC) method can be applied to simulate brachytherapy treatment planning. The MCNP5 c...
The propagation of radiation source uncertainties in spent nuclear fuel (SNF) cask shielding calcula...
An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation ha...
Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will...
In radionuclide metrology, Monte Carlo (MC) simulation is widely used to compute parameters associat...
Fast and accurate predictions of uncertainties in the computed dose are crucial for the determinatio...
The Monte Carlo method provides powerful geometric modeling capabilities for large problem domains i...
This is a technical report prepared by J.D. Smith and E. Galvin on research conducted by interns at ...
Uncertainty propagation to keff using a Total Monte Carlo sampling process is commonly used to solve...
Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code w...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
In analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simulation. T...
AbstractIn analyzing residual radiation, researchers generally use a two-step Monte Carlo (MC) simul...
In activation calculations, there are several approaches to quantify uncertainties: deterministic by...
With the advent of more powerful, less expensive computing resources, more and more attention is bei...
The Monte Carlo (MC) method can be applied to simulate brachytherapy treatment planning. The MCNP5 c...
The propagation of radiation source uncertainties in spent nuclear fuel (SNF) cask shielding calcula...
An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation ha...
Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will...
In radionuclide metrology, Monte Carlo (MC) simulation is widely used to compute parameters associat...
Fast and accurate predictions of uncertainties in the computed dose are crucial for the determinatio...
The Monte Carlo method provides powerful geometric modeling capabilities for large problem domains i...
This is a technical report prepared by J.D. Smith and E. Galvin on research conducted by interns at ...
Uncertainty propagation to keff using a Total Monte Carlo sampling process is commonly used to solve...
Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code w...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...