Underestimation of nuclear fuel burnup – theory, demonstration and solution in numerical models

Monte Carlo methodology provides reference statistical solution of neutron transport criticality problems of nuclear systems. Estimated reaction rates can be applied as an input to Bateman equations that govern isotopic evolution of reactor materials. Because statistical solution of Boltzmann equati...

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Bibliographic Details
Main Authors: Gajda Paweł, Kępisty Grzegorz, Orliński Michał
Format: Article
Language:English
Published: EDP Sciences 2016-01-01
Series:E3S Web of Conferences
Online Access:http://dx.doi.org/10.1051/e3sconf/20161000022