Investigation of Neutronic Performance in Fixed Bed Nuclear Reactor (FBNR) With Fuelled (239Pu/Th)O2
Küçük Resim Yok
Tarih
2013
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Gazi Univ
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
In this study, the neutronic performance analysis in a fixed bed modular nuclear reactor (FBNR) was performed. The effect of the (Pu-239/Th)O-2 mixture fuel of neutronic performance were investigated. Neutronic calculations were conducted by using SCALES code. Firstly, criticality (k(eff)) value compared 9 % enrichment UO2 was computed. The mixture fuel ratio was obtained as % 6 (PuO2)-Pu-239 + % 94. As a result, the operation times passed until the k(eff) value reached a level of 1.06 was computed as similar to 5 year whereas, the corresponding burnup value wase obtained as similar to 33 000 MWD/T.
Açıklama
Anahtar Kelimeler
Fixed bed nuclear reactor (FBNR), Thorium, Fissile fuel
Kaynak
Journal of Polytechnic-Politeknik Dergisi
WoS Q Değeri
N/A
Scopus Q Değeri
Cilt
16
Sayı
4
