Neutronic examination of the U-Mo accident tolerant fuel for VVER-1200 reactors
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Tarih
2024
Yazarlar
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Korean Nuclear Soc
Erişim Hakkı
info:eu-repo/semantics/openAccess
Özet
In this study, we investigated the possibility of employing accident tolerant fuel (ATF) in VVER-1200/V491 assembly without gadolinium-containing fuel rods using the Monte Carlo code Serpent 1.1.7 with ENDF/B-VII cross-section library. The analysis involves assembly design with reflective boundary conditions. To compare the neutronic performances, U-5Mo, U-7.5Mo, U-10Mo, and U-15Mo fuels were chosen in addition to ordinary UO2 2 fuel. The concentration of 135 Xe, 149 Sm, fissile and fertile isotopes with burnup, reactivity feedback with fuel temperature variation, and beta eff values were calculated. The results indicate that the fuel cycle length increases by 54.27% for U-5Mo, 32.6% for U-7.5Mo, and 13.8% for U-10Mo, while it decreases by 16.4% for U-15Mo fuel. Additionally, the effect of 95 Mo content in natural Mo was investigated by reducing the 95 Mo concentration. According to the results, each proposed fuel's fuel cycle length extended when the depletion ratio of 95 Mo increased. Additionally, the calculations for reactivity feedback guarantee safe operating conditions for all UxMo fuels.
Açıklama
Anahtar Kelimeler
VVER-1200, Accident-tolerant fuel (ATF), U-Mo, Serpent, Depleted Mo, FeCrAl, Niobium
Kaynak
Nuclear Engineering and Technology
WoS Q Değeri
Q1
Scopus Q Değeri
Q1
Cilt
56
Sayı
7
