Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets
| dc.contributor.author | ŞAHİN, Sümer | |
| dc.contributor.author | ŞARER, Başar | |
| dc.contributor.author | ÇELİK, Yurdunaz | |
| dc.date.accessioned | 2022-08-05T12:13:06Z | |
| dc.date.available | 2022-08-05T12:13:06Z | |
| dc.date.issued | 2015-01-25 | |
| dc.description.abstract | The 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. | |
| dc.identifier.uri | http://hdl.handle.net/20.500.11905/1504 | |
| dc.language.iso | en | |
| dc.publisher | International Journal of Hydrogen Energy | |
| dc.subject | energy systems engineering | |
| dc.title | Energy multiplication and fissile fuel breeding limits of accelerator-driven systems with uranium and thorium targets | |
| dc.type | Article | |
| dspace.entity.type |