Investigation of (n,?) reactions in fissionable fluids in a hybrid reactor system
Küçük Resim Yok
Tarih
2014
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Carl Hanser Verlag
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
In this study, the effect of (n,gamma) reactions in spent fuel-grade (SFG)-PuO2, UO2, NpO2 and UCO contents was investigated in a designed hybrid reactor system. In this system, the molten salt-heavy metal mixtures 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2-10% UO2, 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2-10 % NpO2, 93-85 % Li20Sn80 + 5 % SFG-PuO2 and 2 10 % UCO were used as fluids. Beryllium (Be) is used as neutron multiplier by (n,2n) reactions. Thence, a Be zone with a width of 3 cm was used in order to contribute on fissile fuel breeding between the liquid first wall and blanket. (n,gamma) reactions were calculated in the liquid first wall, blanket and shield zones, which SFG-PuO2, UO2, NpO2 and UCO contents. 9Cr2WVTa ferritic steel with the width of 4 cm was used as the structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code and nuclear data library ENDF/B-VII.0.
Açıklama
Anahtar Kelimeler
3-Dimensional Neutronic Calculations, Structural Material, Apex Reactor, Radiation-Damage, Fusion
Kaynak
Kerntechnik
WoS Q Değeri
Q4
Scopus Q Değeri
N/A
Cilt
79
Sayı
3
