Analysis of temperature distribution, burn-up and breeding parameters in nuclear fuel rod in fusion-fission reactor system fueled with mixed ThO2-UO2 fuel
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, cilt.35, sa.2, ss.112-122, 2011 (SCI-Expanded, Scopus)
- Yayın Türü: Makale / Tam Makale
- Cilt numarası: 35 Sayı: 2
- Basım Tarihi: 2011
- Doi Numarası: 10.1002/er.1771
- Dergi Adı: INTERNATIONAL JOURNAL OF ENERGY RESEARCH
- Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
- Sayfa Sayıları: ss.112-122
- Süleyman Demirel Üniversitesi Adresli: Evet
Özet
Temperature distribution in nuclear fuel rod, burn-up (BU), possibility of nuclear fuel rejuvenation and breeding parameters are investigated for different coolants under various first wall loads (Pw = 2, 5 and 7 MW m (-2)) in a deuterium-tritium driven fusion-fission reactor system, fueled with mixed UO2-ThO2 fuel. The fuel mixture is considered to be mixed with various mixture fractions.