Work

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.
Language: English
Open Access status: hybrid
OpenAlex ID: W4410190983
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Cites: 30
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Related to: 10