Investigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor

Basit Öğe Kaydı
dc.authoridSahin, Necmettin -- 0000-0002-5756-4216; Tunc, Guven -- 0000-0001-7038-8168
dc.contributor.authorŞahin, Hacı Mehmet
dc.contributor.authorTunç, Güven
dc.contributor.authorŞahin, Necmettin
dc.date.accessioned13.07.201910:50:10
dc.date.accessioned2019-07-29T19:28:01Z
dc.date.available13.07.201910:50:10
dc.date.available2019-07-29T19:28:01Z
dc.date.issued2016
dc.departmentMühendislik Fakültesi
dc.description17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Istanbul, TURKEY
dc.descriptionWOS:000375886400012
dc.description.abstractThe aim of this study is to investigate tritium breeding ratio (TBR) and first wall material damage parameters such as displacement per atom (DPA), gas production of various coolants with Li2C2 tritium breeding material using the three different data libraries (ENDF/B.V, ENDF/B.VI and CLAW IV). Hence, FLiNaK, enriched (90% Li-6) natural lithium, lithium lead eutectic alloy (Li17Pb83) and FLiBe (Li2BeF4) were used as a coolant (moderator) material for the calculation of the tritium breeding ratio and gas production parameters in a hybrid reactor. Neutronic calculations were performed by Monte Carlo Neutron-Particle Transport code MCNPS version 1.40 under a neutron wall loud of 2.25 MW/m(2) (10(14) n/s) by full reactor power for one year. All examined coolant materials were achieved minimum required tritium breeding ratio (TBR > 1.05) and based on radiation damage limits. When the enriched (90%) lithium coolant with lithium carbide breeder used in fusion fission (hybrid) reactor, vanadium alloy first wall will be replaced every 3.6 and 6.7 years for DPA and Helium production, respectively. Copyright (C) 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved.
dc.description.sponsorshipAtilim Univ, Gazi Univ
dc.identifier.doi10.1016/j.ijhydene.2015.11.174
dc.identifier.endpage7075en_US
dc.identifier.issn0360-3199
dc.identifier.issn1879-3487
dc.identifier.issue17en_US
dc.identifier.scopusqualityQ1
dc.identifier.startpage7069en_US
dc.identifier.urihttps://doi.org/10.1016/j.ijhydene.2015.11.174
dc.identifier.urihttps://hdl.handle.net/20.500.12451/5971
dc.identifier.volume41en_US
dc.identifier.wosWOS:000375886400012
dc.identifier.wosqualityN/A
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherElsevier Ltd.
dc.relation.ispartofInternational Journal of Hydrogen Energy
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı
dc.rightsinfo:eu-repo/semantics/embargoedAccess
dc.subjectTritium Breeding Ratio (TBR)
dc.subjectRadiation Damage
dc.subjectFusion-fission Hybrid Reactor
dc.titleInvestigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor
dc.typeArticle

Dosyalar

Orijinal paket
Listeleniyor 1 - 1 / 1
[ X ]
İsim:
sahin-haci mehmet-2016.pdf
Boyut:
1.05 MB
Biçim:
Adobe Portable Document Format
Açıklama:
Tam Metin / Full Text
İndir

Koleksiyon

Makale Koleksiyonu
Scopus İndeksli Yayınlar Koleksiyonu
WoS İndeksli Yayınlar Koleksiyonu