The fission source convergence of a very loosely coupled array of 36 fuel subassemblies with slightly non-symmetric reflection is studied. The fission source converges very slowly from a uniform guess to the fundamental mode in which about 40% of the fissions occur in one corner subassembly. Eigenvalue and fission source estimates are analyzed using a set of statistical tests similar to those used in MCNP, including the ''drift-in-mean'' test and a new drift-in-mean test using a linear fit to the cumulative estimate drift, the Shapiro-Wilk test for normality, the relative error test, and the ''1/N'' test. The normality test does not detect a drifting eigenvalue or fission source. Applied to eigenvalue estimates, the other tests generally fa...
The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a...
We describe recent experience and results from implementing a fission matrix capability into the MCN...
Detailed information on the fission process can be inferred from the observation, modeling and theor...
In order to avoid calculation bias and increase calculation efficiency, convergence of the fission s...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
In Monte Carlo (MC) criticality calculations, source error propagation through the stationary cycles...
Fission source convergence in Monte Carlo criticality calculations can be difficult for some types o...
In order to accurately estimate uncertainty of fission source distribution in a Monte Carlo calculat...
In the solution of the neutron transport equation, the k-effective eigenvalue is related to the aver...
Criticality calculations use the source iteration method and serve an increasingly prominent role in...
We propose a fission source convergence acceleration method for Monte Carlo criticality simulation. ...
Because of the accuracy and ease of implementation, the Monte Carlo methodology is widely used in th...
This paper presents a new response matrix based solver implemented in the Serpent 2 Monte Carlo code...
This paper discusses the source convergence of Monte Carlo calculations for α-eigenvalues. Compared ...
It has been observed that statistical uncertainties on tallies in Monte Carlo iterated-fission-sourc...
The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a...
We describe recent experience and results from implementing a fission matrix capability into the MCN...
Detailed information on the fission process can be inferred from the observation, modeling and theor...
In order to avoid calculation bias and increase calculation efficiency, convergence of the fission s...
The issue of fission source convergence in Monte Carlo eigenvalue calculations is of interest becaus...
In Monte Carlo (MC) criticality calculations, source error propagation through the stationary cycles...
Fission source convergence in Monte Carlo criticality calculations can be difficult for some types o...
In order to accurately estimate uncertainty of fission source distribution in a Monte Carlo calculat...
In the solution of the neutron transport equation, the k-effective eigenvalue is related to the aver...
Criticality calculations use the source iteration method and serve an increasingly prominent role in...
We propose a fission source convergence acceleration method for Monte Carlo criticality simulation. ...
Because of the accuracy and ease of implementation, the Monte Carlo methodology is widely used in th...
This paper presents a new response matrix based solver implemented in the Serpent 2 Monte Carlo code...
This paper discusses the source convergence of Monte Carlo calculations for α-eigenvalues. Compared ...
It has been observed that statistical uncertainties on tallies in Monte Carlo iterated-fission-sourc...
The use of Monte Carlo, random number sampling, for neutron transport has been used for about half a...
We describe recent experience and results from implementing a fission matrix capability into the MCN...
Detailed information on the fission process can be inferred from the observation, modeling and theor...