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math.PR2019
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…
math.PR2019
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.…