Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets | Atılım Üniversitesi Açık Erişim Sistemi
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Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets
Oluşturulma Tarihi: 05-11-2015
Niteleme Bilgileri
Tür: Makale
Yayınlanma Durumu: Yayınlanmış
Dosya Biçimi: Dosya Yok
Dil: İngilizce
Konu(lar): TEKNOLOJİ,
Yazar(lar): Şahin, Sümer (Yazar), Şarer, Başar (Yazar), Çelik, Yurdunaz (Yazar),
Emeği Geçen(ler):
Yayın Adı: International Journal of Hydrogen Energy
Yayın Niteleme Bilgileri: Kaynağın tam metnine ulaşmak için URL’ ye tıklayınız.
Dosya:
Dosya Yok
Accelerator driven systems; Thorium; Uranium; Energy multiplication; Fissile fuel breeding; Nuclear hydrogen production
The study analyses the integral 233U and 239Pu breeding rates, neutron multiplication ratio through (n,xn)- and fission-reactions, heat release, energy multiplication and consequently the energy gain factor in infinite size thorium and uranium as breeder material in an accelerator driven systems (ADS), irradiated by a 1-GeV proton source. Energy gain factor has been calculated as Menergy = 1.67, 4.03 and 5.45 for thorium, depleted uranium (100% 238U) and natural uranium, respectively, where the infinite criticality values are k∞ = 0.40, 0.752 and 0.816. Fissile fuel material production is calculated as 53 232Th(n,γ)233U, 80.24 and 90.65 238U(n,γ)239Pu atoms per incident proton, respectively.
The neutron spectrum maximum is by ∼1 MeV. Lower energy neutrons E < 1 MeV have major contribution on fissile fuel material breeding (>97.5%), whereas their share on energy multiplication is negligible (0.2%) for thorium, depleted uranium. Major fission events occur in the energy interval 1MeV < E < 50 MeV.
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