Investigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor
Yükleniyor...
Tarih
2016
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Elsevier Ltd.
Erişim Hakkı
info:eu-repo/semantics/embargoedAccess
Özet
The 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.
Açıklama
17th International Conference on Emerging Nuclear Energy Systems (ICENES) -- OCT 04-08, 2015 -- Istanbul, TURKEY
WOS:000375886400012
WOS:000375886400012
Anahtar Kelimeler
Tritium Breeding Ratio (TBR), Radiation Damage, Fusion-fission Hybrid Reactor
Kaynak
International Journal of Hydrogen Energy
WoS Q Değeri
N/A
Scopus Q Değeri
Q1
Cilt
41
Sayı
17
