Please use this identifier to cite or link to this item: https://hdl.handle.net/20.500.11851/6471
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dc.contributor.authorÜbeyli, Mustafa-
dc.date.accessioned2021-09-11T15:36:44Z-
dc.date.available2021-09-11T15:36:44Z-
dc.date.issued2008en_US
dc.identifier.citation8th International Symposium on Fusion Nuclear Technology -- SEP 30-OCT 05, 2007 -- Heidelberg, GERMANYen_US
dc.identifier.issn0920-3796-
dc.identifier.issn1873-7196-
dc.identifier.urihttps://doi.org/10.1016/j.fusengdes.2008.06.036-
dc.identifier.urihttps://hdl.handle.net/20.500.11851/6471-
dc.description.abstractA new magnetic fusion reactor design called APEX uses a liquid wall between fusion plasma and solid first wall to reach high neutron wall loads and eliminate the replacement of the first wall structure during the reactor's operation. In this paper, the radiation damage behavior of various first wall materials (W-5Re, V-4Cr-4Ti and SiC/SiC composite) was investigated in the APEX blanket where a protective liquid wall of 75% LiF-23% ThF4-2% (UF4)-U-233 was considered. Tritium breeding potential of this salt with respect to the investigated structural materials was also examined in this blanket. Neutron transport calculations were carried out with the aid of the code, SCALE4.3 by solving the Boltzmann transport equation. Computations were performed with respect to the liquid wall thickness to determine the effective thickness satisfying both the radiation damage and the tritium breeding criteria. Numerical results showed that the flowing wall consisting of 75% LiF-23%ThF4-2% (UF4)-U-233 With a thickness of similar to 35 cm and similar to 50 cm would be required to extend the lifetime of the first wall to similar to 30 years and to supply sufficient tritium to the (DT) fusion driver for W-5Re and V-4Cr-4Ti, respectively whereas, SiC/SiC composite would require a flowing wall thickness of >60 cm to comply with both the damage and the tritium limits. (C) 2008 Elsevier B.V. All rights reserved.en_US
dc.description.sponsorshipForschungszentrum Karlsruheen_US
dc.language.isoenen_US
dc.publisherElsevier Science Saen_US
dc.relation.ispartofFusion Engineering And Designen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectRadiation damageen_US
dc.subjectAtomic displacementen_US
dc.subjectHelium generationen_US
dc.subjectTritium breedingen_US
dc.titleDamage Study for Various Materials at the First Wall of a Magnetic Fusion Reactor Using Protective Liquid Wallen_US
dc.typeConference Objecten_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.volume83en_US
dc.identifier.issue10-12en_US
dc.identifier.startpage1508en_US
dc.identifier.endpage1511en_US
dc.authorid0000-0002-7809-0283-
dc.identifier.wosWOS:000262224300033en_US
dc.identifier.scopus2-s2.0-56949104055en_US
dc.institutionauthorÜbeyli, Elif Derya-
dc.identifier.doi10.1016/j.fusengdes.2008.06.036-
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.relation.conference8th International Symposium on Fusion Nuclear Technologyen_US
dc.identifier.scopusqualityQ1-
item.openairetypeConference Object-
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
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