Please use this identifier to cite or link to this item: https://hdl.handle.net/20.500.11851/7203
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dc.contributor.authorÜbeyli, Mustafa-
dc.date.accessioned2021-09-11T15:55:57Z-
dc.date.available2021-09-11T15:55:57Z-
dc.date.issued2006en_US
dc.identifier.issn0022-3115-
dc.identifier.issn1873-4820-
dc.identifier.urihttps://doi.org/10.1016/j.jnucmat.2006.08.023-
dc.identifier.urihttps://hdl.handle.net/20.500.11851/7203-
dc.description.abstractEvaluating radiation damage characteristics of structural materials considered to be used in fusion reactors is very crucial. In fusion reactors, the highest material damage occurs in the first wall because it will be exposed to the highest neutron, gamma ray and charged particle currents produced in the fusion chamber. This damage reduces the lifetime of the first wall material and leads to frequent replacement of this material during the reactor operation period. In order to decrease operational cost of a fusion reactor, lifetime of the first wall material should be extended to reactor's lifetime. Using a protective flowing liquid wall between the plasma and first wall can decrease the radiation damage on first wall and extend its lifetime to the reactor's lifetime. In this study, radiation damage characterization of various low activation materials used as first wall material in a magnetic fusion reactor blanket using a liquid wall was made. Various coolants (Flibe, Flibe + 4% mol ThF4, Flibe + 8% mol ThF4, Li20Sn80) were used to investigate their effect on the radiation damage of first wall materials. Calculations were carried out by using the code Scale4.3 to solve Boltzmann neutron transport equation. Numerical results brought out that the ferritic steel with Flibe based coolants showed the best performance with respect to radiation damage. (c) 2006 Elsevier B.V. All rights reserved.en_US
dc.language.isoenen_US
dc.publisherElsevieren_US
dc.relation.ispartofJournal of Nuclear Materialsen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subject[No Keywords]en_US
dc.titleOn the radiation damage characterization of candidate first wall materials in a fusion reactor using various molten saltsen_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.volume359en_US
dc.identifier.issue3en_US
dc.identifier.startpage192en_US
dc.identifier.endpage201en_US
dc.authorid0000-0002-7809-0283-
dc.identifier.wosWOS:000243144000005en_US
dc.identifier.scopus2-s2.0-33751313595en_US
dc.institutionauthorÜbeyli, Elif Derya-
dc.identifier.doi10.1016/j.jnucmat.2006.08.023-
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.identifier.scopusqualityQ1-
item.fulltextNo Fulltext-
item.openairecristypehttp://purl.org/coar/resource_type/c_18cf-
item.languageiso639-1en-
item.cerifentitytypePublications-
item.openairetypeArticle-
item.grantfulltextnone-
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
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