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dc.contributor.authorKošťál, Michal
dc.contributor.authorVeškrna, Martin
dc.contributor.authorCvachovec, František
dc.contributor.authorJánský, Bohumil
dc.contributor.authorNovák, Evžen
dc.contributor.authorRypar, Vojtěch
dc.contributor.authorMilčák, Ján
dc.contributor.authorLosa, Evžen
dc.contributor.authorMravec, Filip
dc.contributor.authorMatěj, Zdeněk
dc.contributor.authorRejchrt, Jiří
dc.contributor.authorHarper, Sterling
dc.contributor.authorForget, Benoit Robert Yves
dc.date.accessioned2017-09-08T15:39:51Z
dc.date.available2017-09-08T15:39:51Z
dc.date.issued2015-05
dc.date.submitted2015-04
dc.identifier.issn0306-4549
dc.identifier.urihttp://hdl.handle.net/1721.1/111160
dc.description.abstractThe present paper aims to compare the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor. The calculation is realized with MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Additionally, comparisons between the slowing down power of each media were performed. The slowing down properties are important parameters affecting the thickness of moderator media in a reactor.en_US
dc.language.isoen_US
dc.publisherElsevieren_US
dc.relation.isversionofhttp://dx.doi.org/10.1016/j.anucene.2015.04.011en_US
dc.rightsCreative Commons Attribution-NonCommercial-NoDerivs Licenseen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/4.0/en_US
dc.sourceProf. Forget via Chris Sherratten_US
dc.titleComparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactoren_US
dc.title.alternativeComparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactoren_US
dc.typeArticleen_US
dc.identifier.citationKošťál, Michal et al. “Comparison of Fast Neutron Spectra in Graphite and FLINA Salt Inserted in Well-Defined Core Assembled in LR-0 Reactor.” Annals of Nuclear Energy 83 (September 2015): 216–225 © 2015 Elsevier Ltden_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.mitauthorForget, Benoit Robert Yves
dc.relation.journalAnnals of Nuclear Energyen_US
dc.eprint.versionOriginal manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/NonPeerRevieweden_US
dspace.orderedauthorsKošťál, Michal; Veškrna, Martin; Cvachovec, František; Jánský, Bohumil; Novák, Evžen; Rypar, Vojtěch; Milčák, Ján; Losa, Evžen; Mravec, Filip; Matěj, Zdeněk; Rejchrt, Jiří; Forget, Benoit; Harper, Sterlingen_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0003-1459-7672
mit.licensePUBLISHER_CCen_US


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