Neutronic performance analysis of U–Mn fuel and MgO-BeO tube material in the dual fluid reactor
Yazarlar (2)
Arş. Gör. Semra DAYDAŞ Sinop Üniversitesi, Türkiye
Doç. Dr. Ali TİFTİKÇİ Sinop Üniversitesi, Türkiye
Makale Türü Açık Erişim Özgün Makale (SSCI, AHCI, SCI, SCI-Exp dergilerinde yayınlanan tam makale)
Dergi Adı Nuclear Engineering and Technology (Q1)
Dergi ISSN 1738-5733 Dergi Bilgileri (2026)
Dergi Tarandığı Indeksler SCI-Expanded
Makale Dili Türkçe Basım Tarihi 01-2026
Kabul Tarihi – Yayınlanma Tarihi 01-04-2026
Cilt / Sayı / Sayfa 58 / 4 / 104079–0 DOI 10.1016/j.net.2025.104079
Makale Linki https://doi.org/10.1016/j.net.2025.104079
UAK Araştırma Alanları
Reaktör Teknolojisi Nükleer Teknoloji
Özet
This study investigates the feasibility of using a Uranium–Manganese (U–Mn) alloy as an alternative fuel for the Dual Fluid Reactor (DFR m) concept to increase the temperature margin, along with a Magnesium Oxide–Beryllium Oxide (MgO–BeO) ceramic fuel tube. Neutronic analyses were performed using the SERPENT 1.1. 7 Monte Carlo code with the ENDF/B-VII cross-section library to evaluate fuel performance, reactivity behavior, and safety margins. The results indicate that the U–Mn fuel exhibits lower values and shorter fuel cycle length to those of the U–Cr fuel, while providing the advantage of a lower eutectic temperature. Reactivity coefficients found to be negative for both fuel and coolant with the SiC fuel tube, ensuring inherent safety during temperature excursions. However, for the MgO–BeO configuration, the reactivity coefficients for MgO-BeO were found to be positive, which represents a critical …
Anahtar Kelimeler
Dual fluid reactor | High temperature reactor | Lead-cooled reactor | Magnesium Oxide–Beryllium oxide | Molten-salt reactor | Uranium–manganese