Published September 1996 | Version v1
Journal article

Np and Pu co-recovery in PUREX process for FBR spent fuel

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

Description

Effective use and optimum management of minor actinides are very important for the advanced nuclear fuel recycling. At present, only U and Pu are recovered in the PUREX recycling and it is desirable to isolate minor actinides at high yields without complicating the chemical steps as possible. This report describes a test study for co-recovery of Np and Pu by PUREX method. A flow sheet was prepared aiming at a quantitative extraction of Np through the co-elimination step and a quantitative counter-current extraction of Np in the distribution step. And it was confirmed that almost all amount of Np could be transferred to Pu·U product. Under the coexistence with Pu(6), Np was extracted following its oxidation to Np(6) and then reduced to Pu(3) and Np(5) using hydroxyaminonitrate (HAN). By a multi-step counter current extraction with the solution in which 20% of Pu was in oxidized form Np was recovered along with Pu·U mixture. (M.N.)

Additional details

Publishing Information

Journal Title
Donen Giho
Journal Issue
no.99
Journal Page Range
p. 87-92.
ISSN
0289-6605
CODEN
DOGIEL