Purex co-processing of spent LWR fuels: flow sheet


Zabunoglu O., Ozdemir L.

ANNALS OF NUCLEAR ENERGY, cilt.32, ss.151-162, 2005 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 32 Konu: 2
  • Basım Tarihi: 2005
  • Doi Numarası: 10.1016/j.anucene.2004.07.015
  • Dergi Adı: ANNALS OF NUCLEAR ENERGY
  • Sayfa Sayıları: ss.151-162

Özet

Purex co-processing of spent LWR fuel is investigated. In purex co-processing, uranium and plutonium in spent fuel are processed and recovered together as a single stream, while in standard purex reprocessing uranium and plutonium are obtained as separate streams. A two-step (co-decontamination and co-stripping) flow sheet for purex co-processing is devised; concentrations, recoveries and decontamination factors are calculated; and methods to co-convert uranium-plutonium nitrate to mixed oxide are reviewed. A closed nuclear fuel cycle in which at no point uranium and plutonium are separated from each other is reached. (C) 2004 Elsevier Ltd. All rights reserved.