Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

  • Deng, Nianbiao (School of Nuclear Science and Technology, University of South China) ;
  • Yu, Tao (School of Nuclear Science and Technology, University of South China) ;
  • Xie, Jinsen (School of Nuclear Science and Technology, University of South China) ;
  • Chen, Zhenping (School of Nuclear Science and Technology, University of South China) ;
  • Xie, Qin (School of Nuclear Science and Technology, University of South China) ;
  • Zhao, Pengcheng (School of Nuclear Science and Technology, University of South China) ;
  • Liu, Zijing (School of Nuclear Science and Technology, University of South China) ;
  • Zeng, Wenjie (School of Nuclear Science and Technology, University of South China)
  • Received : 2018.07.20
  • Accepted : 2018.10.24
  • Published : 2019.04.25
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Abstract

Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversion ratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnup increases to 13400 MWd/tU. Thus, the simulation in this paper with the fuel in the 37-element bundle cell using discrete TU fuel pins can be considered to be applied in CANDU-6 reactor with adequate modifications of the core structure and operating modes.

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