Neutronic performance of proliferation hardened thorium fusion breeders
Yükleniyor...
Tarih
2001
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Elsevier Science Sa
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
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.
Açıklama
Anahtar Kelimeler
Kaynak
Fusion Engineering and Design
WoS Q Değeri
Scopus Q Değeri
Q2
Cilt
54
Sayı
1
