Monte Carlo methods for the neutron transport equation

Cox, Alexander M G, Harris, Simon C, Kyprianou, Andreas E and Wang, Minmin (2022) Monte Carlo methods for the neutron transport equation. SIAM-ASA Journal on Uncertainty Quantification, 10 (2). ISSN 2166-2525

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This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [13], [28] and [25], which describes the density (equiv. flux) of neutrons through inhomogeneous fissile medium. Our aim is to analyse existing and novel Monte Carlo (MC) algorithms, aimed at simu- lating the lead eigenvalue associated with the underlying model. This quantity is of principal importance in the nuclear regula- tory industry for which the NTE must be solved on complicated inhomogenous domains corresponding to nuclear reactor cores, irradiative hospital equipment, food irradiation equipment and so on. We include a complexity analysis of such MC algorithms, noting that no such undertaking has previously appeared in the literature. The new MC algorithms offer a variety of advantages and disadvantages of accuracy vs cost, as well as the possibility of more convenient computational parallelisation.

Item Type: Article
Keywords: Monte Carlo, neutron transport
Schools and Departments: School of Mathematical and Physical Sciences > Mathematics
Research Centres and Groups: Probability and Statistics Research Group
SWORD Depositor: Mx Elements Account
Depositing User: Mx Elements Account
Date Deposited: 06 Jan 2022 08:37
Last Modified: 11 Aug 2022 11:15

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