ŞAHİN, SümerŞARER, BaşarÇELİK, Yurdunaz2022-08-052022-08-052015-01-25http://hdl.handle.net/20.500.11905/1504The 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 ¼ 1.67, 4.03 and 5.45 for thorium, depleted uranium (100% 238U) and natural uranium, respectively, where the infinite criticality values are k∞ ¼ 0.40, 0.752 and 0.816. Fissile fuel material production is calculated as 53 232Th(n,g) 233U, 80.24 and 90.65 238U(n,g) 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.enenergy systems engineeringArticle