Monte-Carlo Methods for the Neutron Transport Equation
| Autor: | Alexander M. G. Cox, Simon C. Harris, Andreas E. Kyprianou, Minmin Wang |
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| Rok vydání: | 2020 |
| Předmět: |
Statistics and Probability
Doob h-transform Perron–Frobenius decomposition Applied Mathematics neutron transport equation Probability (math.PR) Numerical Analysis (math.NA) semigroup theory 82D75 60J80 60J75 60J99 principal eigenvalue Modelling and Simulation Modeling and Simulation twisted Monte Carlo FOS: Mathematics Discrete Mathematics and Combinatorics Mathematics - Numerical Analysis Statistics Probability and Uncertainty complexity Mathematics - Probability Monte Carlo simulation |
| Zdroj: | Cox, A M G, Harris, S C, Kyprianou, A E & Wang, M 2022, ' Monte-Carlo Methods for the Neutron Transport Equation ', SIAM/ASA Journal on Uncertainty Quantification, vol. 10, no. 2, pp. 775-825 . https://doi.org/10.1137/21M1390578 |
| ISSN: | 2166-2525 |
| DOI: | 10.48550/arxiv.2012.02864 |
| Popis: | This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [arXiv:1809.00827v2], [arXiv:1810.01779v4] and [arXiv:1901.00220v3], which describes the flux of neutrons through inhomogeneous fissile medium. Our aim is to analyse existing and novel Monte-Carlo (MC) algorithms, aimed at simulating the lead eigenvalue associated with the underlying model. This quantity is of principal importance in the nuclear regulatory industry for which the NTE must be solved on complicated in homogenous 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 parallelization. |
| Databáze: | OpenAIRE |
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