Please use this identifier to cite or link to this item: https://hdl.handle.net/20.500.11851/7126
Full metadata record
DC FieldValueLanguage
dc.contributor.authorYalçın, S.-
dc.contributor.authorÜbeyli, Mustafa-
dc.contributor.authorAcır, A.-
dc.date.accessioned2021-09-11T15:55:45Z-
dc.date.available2021-09-11T15:55:45Z-
dc.date.issued2005en_US
dc.identifier.issn0256-2499-
dc.identifier.issn0973-7677-
dc.identifier.urihttps://doi.org/10.1007/BF02703281-
dc.identifier.urihttps://hdl.handle.net/20.500.11851/7126-
dc.description.abstractIn this study, neutronic investigation of a deuterium-tritium (DT) driven hybrid reactor using ceramic uranium fuels, namely UC, UO2 or UN under a high neutron wall load (NWL) of 10 MW/m(2) at the first wall is conducted over a period of 24 months for fissile fuel breeding for light water reactors (LWRs). New substances, namely, Flinabe or Li20Sn80 are used as coolants in the fuel zone to facilitate heat transfer out of the blanket. Natural lithium is also utilized for comparison to these two innovative coolants. Neutron transport calculations are performed on a simple experimental hybrid blanket with cylindrical geometry with the help of the SCALE 4.3 System by solving the Boltzmann transport equation with the XSDRNPM code in 238 neutron groups and an S-8-P-3 approximation. The investigated blanket using Flinabe or U(2)Osn(80) shows better fissile fuel breeding and fuel enrichment characteristics compared to that with natural lithium which shows that these two innovative coolants can be used in hybrid reactors for higher fissile fuel breeding performance. Furthermore, using a high NWL of 10 MW/m(2) at the first wall of the investigated blanket can decrease the time for fuel rods to reach the level for charging in LWRs.en_US
dc.language.isoenen_US
dc.publisherSpringer Indiaen_US
dc.relation.ispartofSadhana-Academy Proceedings In Engineering Sciencesen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectfusionen_US
dc.subjectfissionen_US
dc.subjecthybrid reactoren_US
dc.subjectfissile fuel breedingen_US
dc.titleNeutronic Analysis of a High Power Density Hybrid Reactor Using Innovative Coolantsen_US
dc.typeArticleen_US
dc.departmentFaculties, Faculty of Engineering, Department of Electrical and Electronics Engineeringen_US
dc.departmentFakülteler, Mühendislik Fakültesi, Elektrik ve Elektronik Mühendisliği Bölümütr_TR
dc.identifier.volume30en_US
dc.identifier.startpage585en_US
dc.identifier.endpage600en_US
dc.authorid0000-0002-7809-0283-
dc.identifier.wosWOS:000232010100007en_US
dc.identifier.scopus2-s2.0-25844443397en_US
dc.institutionauthorÜbeyli, Elif Derya-
dc.identifier.doi10.1007/BF02703281-
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.identifier.scopusqualityQ1-
item.openairetypeArticle-
item.languageiso639-1en-
item.grantfulltextnone-
item.fulltextNo Fulltext-
item.openairecristypehttp://purl.org/coar/resource_type/c_18cf-
item.cerifentitytypePublications-
Appears in Collections:Elektrik ve Elektronik Mühendisliği Bölümü / Department of Electrical & Electronics Engineering
Scopus İndeksli Yayınlar Koleksiyonu / Scopus Indexed Publications Collection
WoS İndeksli Yayınlar Koleksiyonu / WoS Indexed Publications Collection
Show simple item record



CORE Recommender

SCOPUSTM   
Citations

14
checked on Dec 21, 2024

WEB OF SCIENCETM
Citations

16
checked on Nov 2, 2024

Page view(s)

72
checked on Dec 23, 2024

Google ScholarTM

Check




Altmetric


Items in GCRIS Repository are protected by copyright, with all rights reserved, unless otherwise indicated.