Determination of enrichment of recycle uranium fuels for different burnup values


Zabunglu O. H.

ANNALS OF NUCLEAR ENERGY, cilt.35, sa.2, ss.285-290, 2008 (SCI İndekslerine Giren Dergi) identifier identifier

  • Cilt numarası: 35 Konu: 2
  • Basım Tarihi: 2008
  • Doi Numarası: 10.1016/j.anucene.2007.06.008
  • Dergi Adı: ANNALS OF NUCLEAR ENERGY
  • Sayfa Sayıları: ss.285-290

Özet

Uranium (U) recovered from spent LWR fuels by reprocessing, which contains small amounts of U-236, is to be enriched before being re-irradiated as the recycle U. During the enrichment of recovered U in U-235, the mass fraction of U-236 also increases. Since the existence of U-236 in the recycle U has a negative effect on neutron economy, a greater enrichment of U-235 in the recycle U is required for reaching the same burnup as can be reached by the fresh U fuel. Two burnup values play the most important role in determining the enrichment of recycle U: (1) discharge burnup of spent fuel from which the recycle U is obtained and (2) desired discharge burnup of the recycle U fuel. A step-by-step procedure for calculating the enrichment of the recycle U as a function of these two burnup values is introduced. The computer codes MONTEBURNS and ORIGEN-S are made use of and a three-component (U-235, U-236, U-238) enrichment scheme is applied for calculating the amount of U-236 in producing the recycle U from the recovered U. As was aimed, the resulting expression is simple enough for quick/hand calculations of the enrichment of the recycle U for any given discharge burnup of spent fuel and for any desired discharge burnup of the recycle U fuel, most accurately within the range of 33,000-50,000 MWd/tonU. (C) 2007 Elsevier Ltd. All rights reserved.