Published June 1967 | Version v1
Journal article

The purification of plutonium by anion exchange in nitric acid

  • 1. Atomic Fuel Corporation, Tokai, lbaraki (Japan)
  • 2. Sumitomo Atomic Energy Industries, Ltd., Osaka (Japan)

Description

Plutonium nitrate solution stored for long after separation from uranium and fission products by anion-exchange and containing a large amount of hydroxyl-amine hydrochloride used as eluent, was repurified by anion-exchange. Radiochemical determination of plutonium isotopes - both in the purified plutonium solution and waste solution - was also studied. The results were as follows; (1) Pu (IV) was adsorbed on anion-exchange resin (Dowex-1 x 2, 200∼400 mesh) in 7.2 N nitric acid solution at about 60℃, and was eluted with 0.35 N nitric acid. (2) Plutonium was recovered with a yield of 97%. (3) High purity plutonium was obtained leaving 241Am in the waste solution. (author)

Availability note (English)

Available from DOI: https://doi.org/10.1080/18811248.1967.9732746

Additional details

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo) (Online)
Journal Volume
4
Journal Issue
6
Journal Page Range
p. 289-292
ISSN
1881-1248

Optional Information

Notes
12 refs., 3 figs., 1 tab., 1 photo