A Novel Method for Simulating Spectral Nuclear Reactor Criticality by a Spatially Dependent Volume Size Control

DOI10.1007/978-0-8176-8238-5_5zbMATH Open1252.82130OpenAlexW50157311MaRDI QIDQ2909558

Bardo E. J. Bodmann, D. Q. de Camargo, S.d. Q. B. Leite, Marco Túlio Vilhena

Publication date: 30 August 2012

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

Full work available at URL: https://doi.org/10.1007/978-0-8176-8238-5_5

zbMATH Keywords

Monte CarloBoltzmann transport equationneutron transport equationsnuclear reactor criticality

Mathematics Subject Classification ID

Transport processes in time-dependent statistical mechanics (82C70) Nuclear reactor theory; neutron transport (82D75)

Related Items (1)

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

This page was built for publication: A Novel Method for Simulating Spectral Nuclear Reactor Criticality by a Spatially Dependent Volume Size Control

Report a bug (only for logged in users!)Click here to report a bug for this page (MaRDI item Q2909558)