한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)

한국원자력학회 (Korean Nuclear Society)
권호 표지

Optimization of CANFLEX-RU Fuel Bundle for CANDU-6

  • Lee, Y. O. (Korea Atomic Energy Research Institute) ;
  • C. J. Jeong (Korea Atomic Energy Research Institute) ;
  • K. S. Sim (Korea Atomic Energy Research Institute) ;
  • J. S. Jun (Korea Atomic Energy Research Institute) ;
  • Park, G. S. (Korea Atomic Energy Research Institute) ;
  • Kim, B. G. (Korea Atomic Energy Research Institute) ;
  • Park, J. H. (Korea Atomic Energy Research Institute) ;
  • H. C. Suk (Korea Atomic Energy Research Institute)
  • 발행 : 1995.10.01
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초록

Considering the higher discharge burnup, lower channel refuelling rate, lower linear element rating(LER), lower coolant void reactivity and axial power shape, CANFLEX-RU fuel bundle is optimized for CANDU-6 by grading the fissile composition in the ring-wise of the bundle and by applying fuel management scheme appropriately. The fissile composition of the fuel bundle is graded as the recovered uranium (0.9 w/o U-235) in the outer and intermediate elements, depleted Uranium (0.2 w/o U-235) in the center element, natural uranium (0.71 w/o U-235) in the inner elements. Enrichment is not required for these fuel. The fissile composition is optimized by lattice calculation and by time-averaged reactor simulation. CANFLEX-RU optimized for CANDU-6 resulted to be the 15% lower channel refuelling rate, acceptable axial power profile and power envelope, 70% higher discharge burnup, 15% lower LER and not increase coolant void reactivity compared with the 37-element natural uranium bundle for CANDU-6.

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