The production of 238-242Pu(n,?)239-243Pu fissionable fluids in a fusion-fission hybrid reactor
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 spent fuel grade plutonium content on Pu259-243 was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99-95% Li20Sn80-1-5% SFG-Pu, 99-95% Li20Sn80-1-5% SFG-PuF4, 99-95% Li20Sn80-1-5% SFG-PuO2. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of Pu238-242(n,gamma)Pu239-243 was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0.
Açıklama
Anahtar Kelimeler
3-Dimensional Neutronic Calculations, Power Density Concepts, Apex Reactor, Structural Material, Radiation-Damage
Kaynak
Kerntechnik
WoS Q Değeri
Q4
Scopus Q Değeri
N/A
Cilt
79
Sayı
1
