Improvement of the neutronic performance of the hybrid reactor rejuvenating spent fuels using various moderators


Unalan S. , Akansu S. O.

FUSION TECHNOLOGY, cilt.34, ss.109-127, 1998 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 34 Konu: 2
  • Basım Tarihi: 1998
  • Doi Numarası: 10.13182/fst98-a57
  • Dergi Adı: FUSION TECHNOLOGY
  • Sayfa Sayıları: ss.109-127

Özet

Effects on the neutronic performance of the hybrid blanket rejuvenating light water reactor and CANDU spent fuels of moderators (Be, C, and D2O) inserted between the fusion chamber and the fissile zone of deuterium-deuterium and deuterium-tritium-driven hybrid reactor were investigated to obtain the best rejuvenation performance and more energy production. The calculations were carried out for different thicknesses of the moderator zone (DR). In addition, to eliminate focal heating, the analysis was also repeated for reduced radius of the spent fuel rods in the first and the second fuel rows of the fissile zone.