Published September 1999 | Version v1
Book

Spent fuel test of an advanced Purex process: Parc

Description

An advanced PUREX process, PARC process has been developed which can cope with both the reduction of cost and waste arising by simplification of PUREX process and the reduction of long-term toxicity of radioactive waste by the separation and confinement of long-lived nuclides such as 99Tc, 129I, 237Np. Experiment work with spent fuel on the PARC flow sheet including iodine treatment has started. It was shown that the silver impregnated silica-gel captured 129I effectively. Extraction test using butyraldehyde as a reducing reagent showed that the reagent was an effective reductant of Np(VI) in the presence of uranium and plutonium. Tc was separated using high acid

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
Jackson Hole, Wyoming (United States)
Imprint Pagination
7 p.

Conference

Title
International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
Acronym
Global'99
Dates
29 Aug - 3 Sep 1999
Place
Las Vegas, NV (United States)

Optional Information

Notes
11 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)