4 papers
Stochastic Methods for Neutron Transport Equation III: Generational many-to-one and
A. M. G. Cox, E. L. Horton, A. E. Kyprianou +1
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 t…
Stochastic Methods for the Neutron Transport Equation II: Almost sure growth
Simon C. Harris, Emma Horton, Andreas E. Kyprianou
The neutron transport equation (NTE) describes the flux of neutrons across a planar cross-section in an inhomogeneous fissile medium when the process of nuclear fission is active.…
Stochastic Methods for the Neutron Transport Equation I: Linear Semigroup asymptotics
Emma Horton, Andreas E. Kyprianou, Denis Villemonais
The Neutron Transport Equation (NTE) describes the flux of neutrons through an inhomogeneous fissile medium. In this paper, we reconnect the NTE to the physical model of the spatia…
Multi-species neutron transport equation
Alex M. G. Cox, Simon C. Harris, Emma Horton +1
The Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous fissile medium. Whilst well treated in the nuclear physics literature (cf. [9, 27]), the N…