Stochastic Methods for Neutron Transport Equation III: Generational many-to-one and $k_\texttt{eff}$
A. M. G. Cox, E. L. Horton, A. E. Kyprianou, D. Villemonais

TL;DR
This paper advances the probabilistic analysis of the neutron transport equation by rigorously interpreting the key eigenvalue keff, crucial for reactor physics, through Perron-Frobenius and operator methods, enhancing understanding of neutron flux growth and Monte Carlo simulations.
Contribution
It provides the first rigorous probabilistic interpretation of keff in the context of neutron transport, complementing existing engineering and simulation approaches.
Findings
Develops stochastic analysis linking keff to Perron-Frobenius theory.
Provides a rigorous probabilistic framework for neutron flux growth.
Bridges operator analysis with Monte Carlo simulation interpretations.
Abstract
The Neutron Transport Equation (NTE) describes the flux of neutrons over time through an inhomogeneous fissile medium. In the recent articles [5, 10], a probabilistic solution of the NTE is considered in order to demonstrate a Perron-Frobenius type growth of the solution via its projection onto an associated leading eigenfunction. In [9, 4], further analysis is performed to understand the implications of this growth both in the stochastic sense, as well as from the perspective of Monte-Carlo simulation. Such Monte-Carlo simulations are prevalent in industrial applications, in particular where regulatory checks are needed in the process of reactor core design. In that setting, however, it turns out that a different notion of growth takes centre stage, which is otherwise characterised by another eigenvalue problem. In that setting, the eigenvalue, sometimes called k-effective (written…
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Taxonomy
TopicsNuclear reactor physics and engineering · Probabilistic and Robust Engineering Design · Mathematical Approximation and Integration
