Moment Asymptotics for the Neutron Transport Equation
Year: 2025
Type: article
Abstract: Over the last decade, ingenuous developments in Monte Carlo methods have enabled the unbiased estimation of adjoint-weighted reactor parameters expressed as bilinear forms, such as kinetics parameters and sensitivity coefficients. A prominent example is the iterated fission probability method, which relies on the simulation of the fission chains descending from an ancestor neutron: The neutron population at an asymptotic fission generation yields an estimate of the importance function (and hence of the adjoint fundamental eigenmode) at the phase-space coordinates of the ancestor neutron.
Source: Nuclear Science and Engineering
Language: English
Subfield: Aerospace Engineering
Field: Engineering
Domain: Physical Sciences
Open Access status: hybrid
OpenAlex ID: W4410190983
