Positive Solutions for Reactor Multigroup Neutron Transport Systems: Criticality Problem

DOI10.1137/0149051zbMath0679.45012OpenAlexW2057854830MaRDI QIDQ4728818

Gen-Shun Chen, Anthony W. Leung

Publication date: 1989

Published in: SIAM Journal on Applied Mathematics (Search for Journal in Brave)

Full work available at URL: https://doi.org/10.1137/0149051

zbMATH Keywords

upper and lower solutionscriticality problembounded, positive solutionreactor multigroup neutron transportsteady-state multigroup neutron transport equations

Mathematics Subject Classification ID

Integro-partial differential equations (45K05) Statistical mechanics of ferroelectrics (82D45) Transport processes in time-dependent statistical mechanics (82C70)

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Transport equation with delayed neutrons

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