Investigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport code
Küçük Resim Yok
Tarih
2013
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Carl Hanser Verlag
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
In this study, 98-90% Li2BeF4-2-10 % ThF4, 98-90% Li2BeF4-2-10 % UF4, 98-90% Li2BeF4-2-10 % UO2 and 100% Li2BeF4 molten salt-heavy metal was used as fluid. The fluids were used in the liquid first wall, liquid second wall and shield zones of the designed hybrid reactor system. A steel wall of 4 cm thickness is used as structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In the study, the effect of liquid second wall thicknesses (20 cm, 30 cm, 40 cm, 50 cm) on the neutron flux distribution and the parameters of radiation damage according to neutron energy spectrum in the structural material were investigated for the selected fluids. A three-dimensional analysis was done by using the most recent version of the MCNPX-2.7.0 Monte Carlo code and the nuclear data library ENDF/B-VII.
Açıklama
Anahtar Kelimeler
Breeder Apex Reactor, Radiation-Damage, Fusion Breeder, Hylife-Ii, Technology, Design, System, Fuel, Wall
Kaynak
Kerntechnik
WoS Q Değeri
Q4
Scopus Q Değeri
N/A
Cilt
78
Sayı
3
