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, vol.35, no.2, pp.112-122, 2011 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 35 Issue: 2
  • Publication Date: 2011
  • Doi Number: 10.1002/er.1771
  • Journal Name: INTERNATIONAL JOURNAL OF ENERGY RESEARCH
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.112-122
  • Süleyman Demirel University Affiliated: Yes

Abstract

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.