Neutronic performance of proliferation hardened thorium fusion breeders
| dc.contributor.author | Şahín, Sümer | |
| dc.contributor.author | Yapıcı, Hüseyin | |
| dc.contributor.author | Şahin, Necmettin | |
| dc.date.accessioned | 13.07.201910:50:10 | |
| dc.date.accessioned | 2019-07-16T08:24:59Z | |
| dc.date.available | 13.07.201910:50:10 | |
| dc.date.available | 2019-07-16T08:24:59Z | |
| dc.date.issued | 2001 | |
| dc.department | Mühendislik Fakültesi | |
| dc.description.abstract | Production of denaturated fissile fuel in a thorium fusion breeder has been investigated by mixing the fertile fuel with natural-UO2 and LWR (light water reactors) spent nuclear fuel. Four different coolants (pressurized helium, Flibe `Li2BeF4', natural lithium and Li17Pb83 eutectic) are selected for the nuclear heat transfer. In order to obtain a power flattening in the fissile-fertile zone, the UO2- or the spent fuel-fraction in the mixed oxide (MOX) fuel has been gradually increased in radial direction. Power plant operation periods between 13 and 29 months are evaluated to achieve a fissile fuel enrichment approximately 4%, under a first-wall fusion neutron energy current of 5 MW m-2 (plant factor of 100%). For a plant operation over 4 years, enrichment grades between 6.0 and 11.5% are calculated for the investigated MOX fuel and coolant compositions. The 238U component of natural-UO2 can provide a limited proliferation hardening only for the 233U component, whereas, the homogenous mixture of ThO2 with a small quantity of (>4%) LWR spent nuclear fuel remains all-over non-prolific for both, uranium and plutonium components. | |
| dc.identifier.doi | 10.1016/S0920-3796(00)00107-1 | |
| dc.identifier.endpage | 77 | en_US |
| dc.identifier.issn | 0920-3796 | |
| dc.identifier.issue | 1 | en_US |
| dc.identifier.scopusquality | Q2 | |
| dc.identifier.startpage | 63 | en_US |
| dc.identifier.uri | https://dx.doi.org/10.1016/S0920-3796(00)00107-1 | |
| dc.identifier.uri | https://hdl.handle.net/20.500.12451/2993 | |
| dc.identifier.volume | 54 | en_US |
| dc.indekslendigikaynak | Scopus | |
| dc.language.iso | en | |
| dc.publisher | Elsevier Science Sa | |
| dc.relation.ispartof | Fusion Engineering and Design | |
| dc.relation.publicationcategory | Makale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı | |
| dc.rights | info:eu-repo/semantics/closedAccess | |
| dc.title | Neutronic performance of proliferation hardened thorium fusion breeders | |
| dc.type | Article |
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