Three-dimensional Monte Carlo calculation of some nuclear parameters
Küçük Resim Yok
Tarih
2017
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
E D P Sciences
Erişim Hakkı
info:eu-repo/semantics/openAccess
Özet
In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li20Sn80 + 1-5% RG-Pu, 99-95% Li20Sn80 + 1-5% RG-PuF4, and 99-95% Li20Sn80 + 1-5% RG-PuO2, as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Threedimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.
Açıklama
3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (TESNAT) -- MAY 10-12, 2017 -- Adana, TURKEY
Anahtar Kelimeler
Breeder Apex Reactor, Radiation-Damage, Fusion Breeder, Structural Material, Neutronic Calculations, Self-Sufficiency, Hybrid Reactor
Kaynak
3rd International Conference on Theoretical and Experimental Studies in Nuclear Applications and Technology (Tesnat 2017)
WoS Q Değeri
N/A
Scopus Q Değeri
Cilt
154
