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Three Dımensıonal Neutronıc Calculatıons For The Fusıon Breeder Apex Reactor    
Yazarlar
Başer Şarer
Mehtap Günay
İnönü Üniversitesi, Türkiye
Prof. Dr. Aybaba HANÇERLİOĞULLARI
Kastamonu Üniversitesi, Türkiye
Mehmet Emin Korkmaz
Karamanoğlu Mehmetbey Üniversitesi, Türkiye
Özet
Three-dimensional analysis has been made using the MCNP Monte Carlo code and ENDF/B-VI nuclear data. The nuclear characteristics of a fusion-fission hybrid reactor such as tritium breeding ratio, energy multiplication factor, fissile fuel breeding, first wall radiation damage, and heat deposition have been investigated in a liquid first wall, blanket, and shield for the various mixture compositions of molten salt and heavy metals for blanket layer thicknesses of 20, 30, 40, and 50 cm. The neutron flux load at the first wall is assumed to be 10 MW/ m2. The flowing molten salt wall is composed of flibe (Li2BeF4) as the main constituent with increased mole fractions of heavy metals, 2 to 10% ThF4 and UF4. In terms of all parameters, the mixtures with UF4 show better performance than the mixtures with ThF4. The atomic displacement and the helium, tritium production rates remain well below the presumable limits for all mixture compositions of molten salt and heavy metals and thicknesses of the blanket.
Anahtar Kelimeler
Flibe | Fusion | Molten salt
Makale Türü Özgün Makale
Makale Alt Türü SSCI, AHCI, SCI, SCI-Exp dergilerinde yayımlanan tam makale
Dergi Adı Fusıon Science And Technology
Dergi Tarandığı Indeksler SSCI
Makale Dili İngilizce
Basım Tarihi 01-2007
Cilt No 52
Sayı 1
Sayfalar 107 / 115
BM Sürdürülebilir Kalkınma Amaçları
Atıf Sayıları
SCOPUS 23

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