Analysis of temperature distribution, burn-up and breeding parameters in nuclear fuel rod in fusion-fission reactor system fueled with mixed ThO2-UO2 fuel


Ipek O.

INTERNATIONAL JOURNAL OF ENERGY RESEARCH, cilt.35, ss.112-122, 2011 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 35 Konu: 2
  • Basım Tarihi: 2011
  • Doi Numarası: 10.1002/er.1771
  • Dergi Adı: INTERNATIONAL JOURNAL OF ENERGY RESEARCH
  • Sayfa Sayıları: ss.112-122

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.