Neutronic examination of the U–Mo accident tolerant fuel for VVER-1200 reactors
Yazarlar (2)
Arş. Gör. Semra DAYDAŞ Sinop Üniversitesi, Türkiye
Doç. Dr. Ali TİFTİKÇİ Sinop Üniversitesi, Türkiye
| Makale Türü |
Özgün Makale
(SSCI, AHCI, SCI, SCI-Exp dergilerinde yayınlanan tam makale)
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| Dergi Adı | Nuclear Engineering and Technology (Q1) | ||
| Dergi ISSN | 1738-5733 Dergi Bilgileri (2024) | ||
| Dergi Tarandığı Indeksler | SCI-Expanded | ||
| Makale Dili | Türkçe | Basım Tarihi | 02-2024 |
| Cilt / Sayı / Sayfa | 56 / 7 / 2625–2632 | DOI | 10.1016/j.net.2024.02.021 |
| Makale Linki | http://dx.doi.org/10.1016/j.net.2024.02.021 | ||
| UAK Araştırma Alanları |
Reaktör Teknolojisi
Nükleer Malzemeler
Nükleer Teknoloji
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| 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-7.5 Mo, U–10Mo, and U–15Mo fuels were chosen in addition to ordinary UO 2 fuel. The concentration of 135 Xe, 149 Sm, fissile and fertile isotopes with burnup, reactivity feedback with fuel temperature variation, and β eff values were calculated. The results indicate that the fuel cycle length increases by 54.27% for U–5Mo, 32.6% for U-7.5 Mo, 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 … |
| Anahtar Kelimeler |
| Accident-tolerant fuel (ATF) | Depleted Mo | FeCrAl | Niobium | Serpent | U–Mo | VVER-1200 |
Science Direct
Neutronic examination of the U–Mo accident tolerant fuel for VVER-1200 reactors
BM Sürdürülebilir Kalkınma Amaçları
| Atıf Sayıları | |
| Scopus | 10 |
| Google Scholar | 18 |