Abstract Since the 1960s, Monte Carlo methods have been used to compute the effect of
perturbations on system responses and for computing sensitivity coefficients. This review …

A continuous-energy Monte Carlo method is developed to compute adjoint-based k-
eigenvalue sensitivity coefficients with respect to nuclear data. The method is implemented …

The sensitivity and uncertainty analysis tools of the Oak Ridge National Laboratory SCALE
nuclear modeling and simulation code system that have been developed over the last …

This work introduces a new approach for calculating sensitivity coefficients for generalized
neutronic responses to nuclear data uncertainties using continuous-energy Monte Carlo …

Abstract The current Monte Carlo (MC) adjoint-weighted tally techniques based on the
iterated fission probability (IFP) concept require a memory amount which is proportional to …

A generalized perturbation theory (GPT) formulation suited for the Monte Carlo (MC)
eigenvalue calculations is newly developed to estimate sensitivities of a general MC tally to …

Abstract Knowledge of adjoint-weighted kinetics parameters plays an importance role in
analyzing the reactor safety and in describing the transient behavior of nuclear reactors …

This study introduced two new approaches for calculating the importance weighting function
for Contributon and CLUTCH eigenvalue sensitivity coefficient calculations, and compared …

Abstract The continuous-energy Monte Carlo (MC) sensitivity and uncertainty (S/U) analysis
conducted using the multigroup covariance matrices has a theoretical pitfall in that it is …

Monte Carlo radiation transport software is used extensively for determining the effective
multiplication factor k of fissionable systems towards assessing the criticality safety of …