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Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR

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dc.contributor.authorShchurovskaya, M. V.
dc.contributor.authorGeraskin, N. I.
dc.contributor.authorKruglikov, A. E.
dc.contributor.authorЩуровская, Мария Владимировна
dc.contributor.authorГераскин, Николай Иванович
dc.contributor.authorКругликов, Антон Евгеньевич
dc.date.accessioned2024-11-25T15:52:48Z
dc.date.available2024-11-25T15:52:48Z
dc.date.issued2020
dc.description.abstract© 2020 Elsevier LtdIn this study, we analyze different methods for the generation of homogenized few-group cross sections (XS) using continuous-energy Monte Carlo codes Serpent 2.1.29 and MCU–PTR for full-core diffusion calculation of small-size light water research reactors. Few-group reaction cross sections, scattering matrices and diffusion coefficients generated in an infinite lattice model with and without B1-leakage correction of spectra, and in full-scale 3D core calculations, are compared. Few-group XS are used in the TIGRIS diffusion nodal simulator to calculate the simplified cores with IRT-3 M fuel and a light water reflector. Special attention is paid to the impact of diffusion coefficients on the results of diffusion calculations. We compare the following different methods for the generation of diffusion coefficients: the usual “out-scatter” approximation, the transport correction for hydrogen implemented in Serpent, and the migration method implemented in MCU–PTR.
dc.identifier.citationShchurovskaya, M. V. Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR / Shchurovskaya, M.V., Geraskin, N.I., Kruglikov, A.E. // Annals of Nuclear Energy. - 2020. - 141. - 10.1016/j.anucene.2020.107361
dc.identifier.doi10.1016/j.anucene.2020.107361
dc.identifier.urihttps://www.doi.org/10.1016/j.anucene.2020.107361
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85078851336&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000526111300020
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/20206
dc.relation.ispartofAnnals of Nuclear Energy
dc.titleComparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR
dc.typeArticle
dspace.entity.typePublication
oaire.citation.volume141
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