Published January 1989 | Version v1
Book

A flow sheet for the recovery of plutonium and uranium from the scraps of mixed oxide fuel fabrication (Preprint No. ST.15)

  • 1. Bhabha Atomic Research Centre, Bombay (India). Fuel Reprocessing Div.

Description

A flow sheet is proposed for the recovery of plutonium and uranium from the scraps generated during the fabrication of mixed oxide fuels. Uranium is recovered as U3O8 after precipitating as sodium uranyl acetate from the solution obtained by nitric acid, dissolution of ignited scrap material while plutonium is recovered from the supernatant by anion exchange separation using Dowex 1x4. (author)

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre.
Imprint Place
Bombay (India)
Imprint Pagination
2 p.

Conference

Title
Symposium on radiochemistry and radiation chemistry.
Dates
4-7 Jan 1989.
Place
Kalpakkam (India).