On a Parametric Representation of the Angular Neutron Flux in the Energy Range from 1 eV to 10 MeV

DOI10.1007/978-3-030-48186-5_3zbMath1447.82038OpenAlexW3039142925MaRDI QIDQ5115911

Bardo E. J. Bodmann, Luiz F. F. Chaves Barcellos, Marco Túllio de Vilhena

Publication date: 21 August 2020

Published in: Computational and Analytic Methods in Science and Engineering (Search for Journal in Brave)

Full work available at URL: https://doi.org/10.1007/978-3-030-48186-5_3

zbMATH Keywords

Boltzmann equationMonte Carlo simulationneutron flux

Mathematics Subject Classification ID

Monte Carlo methods (65C05) Nuclear reactor theory; neutron transport (82D75) Boltzmann equations (35Q20) Monte Carlo methods applied to problems in statistical mechanics (82M31)

Cites Work

• On a Continuous Energy Monte Carlo Simulator for Neutron Transport: Optimisation with Fission, Intermediate and Thermal Distributions
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