Moment Asymptotics for the Neutron Transport Equation
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.
Authors
- Andrea Zoia (ORCID: https://orcid.org/0000-0002-9099-8956)
- Andreas E. Kyprianou (ORCID: https://orcid.org/0000-0001-7599-2495)
- Emma Horton (ORCID: https://orcid.org/0000-0002-6027-2169)
- Éric Dumonteil (ORCID: https://orcid.org/0000-0001-8331-1944)
Institutions
- Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR)
- Université Paris-Saclay (FR)
- University of Warwick (GB)
- CEA Paris-Saclay (FR)
- Institut de Recherche sur les Lois Fondamentales de l'Univers (FR)
Publication Details
- Journal
- Nuclear Science and Engineering
- Published
- 2025-05-08
- DOI
- https://doi.org/10.1080/00295639.2025.2460328
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00
Funders
- Engineering and Physical Sciences Research Council