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Analysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system

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dc.contributor.authorOjinnaka, C. A. S.
dc.contributor.authorZimin, V. G.
dc.contributor.authorStrashnykh, V. P.
dc.contributor.authorNikonov, S. P.
dc.contributor.authorЗимин, Вячеслав Геннадьевич
dc.contributor.authorСтрашных, Вадим Петрович
dc.date.accessioned2024-11-27T06:58:20Z
dc.date.available2024-11-27T06:58:20Z
dc.date.issued2020
dc.description.abstract© 2020 Elsevier LtdThe switching off of the one of four main circulation pumps results in the Kalinin-3 Coolant Transient Benchmark. The benchmark contains four exercises, but this article shows the results of the exercise two of the VVER-1000 reactor core calculation. Reactor core analysis code SKETCH-N/SKAZKA is used to simulate the steady-state and transient conditions of the VVER reactor. The reactor core boundary conditions for the problem are provided by ATHLET/BIPR-VVER code. In the initial steady-state condition and at the end of the transient the power distribution is compared with the nuclear power plant (NPP) data. The average error in 3-D power distribution is 3.6%. The average difference in fuel assembly (FA) power is less than 2%. In the transient calculation, we compared with the experimental data the reactor power and axial offset. There is close agreement between the numerical results and NPP data.
dc.identifier.citationAnalysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system / Ojinnaka, C.A.S. [et al.] // Annals of Nuclear Energy. - 2020. - 147. - 10.1016/j.anucene.2020.107716
dc.identifier.doi10.1016/j.anucene.2020.107716
dc.identifier.urihttps://www.doi.org/10.1016/j.anucene.2020.107716
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85088955118&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000561485300033
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/22146
dc.relation.ispartofAnnals of Nuclear Energy
dc.titleAnalysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system
dc.typeArticle
dspace.entity.typePublication
oaire.citation.volume147
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