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Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide

  • Alzamly, Mohamed A. (Egyptian Nuclear and Radiological Regulatory Authority (ENRRA)) ;
  • Aziz, Moustafa (Egyptian Nuclear and Radiological Regulatory Authority (ENRRA)) ;
  • Badawi, Alya A. (Department of Nuclear and Radiation Engineering, Faculty of Engineering, University of Alexandria) ;
  • Gabal, Hanaa Abou (Department of Nuclear and Radiation Engineering, Faculty of Engineering, University of Alexandria) ;
  • Gadallah, Abdel Rraouf A. (Egyptian Nuclear and Radiological Regulatory Authority (ENRRA))
  • 투고 : 2019.04.17
  • 심사 : 2019.09.21
  • 발행 : 2020.04.25

초록

We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (Th+Pu)O2, achieved about 24% higher fuel cycle length than the UO2 case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found.

키워드

참고문헌

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피인용 문헌

  1. Effects of 3D contraction on pebble flow uniformity and stagnation in pebble beds vol.53, pp.5, 2020, https://doi.org/10.1016/j.net.2020.10.022