Published March 1994 | Version v1
Journal article Metadata-only

Development of electrolytic dissolution of MOX fuel

Creators

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

Description

A method of electrolytic dissolution has been studied to dissolve plutonium dioxide in nitric acid. This dissolution uses Ag2+ as an ionic catalyst to oxidize PuO2(IV) to PuO22+(VI). Ag2+ is generated by electrolysis of silver nitrate. This method is to be developed for dissolving mixed oxide, or decontamination of plutonium contained in solid wastes in plutonium fuel fabrication facility. This report summarizes the effect of UO2 on PuO2 dissolving velocity with wide range of the MOX in ratio of Pu to U. (author)

Additional details

Publishing Information

Journal Title
Donen Giho
Journal Issue
no.89
Journal Page Range
p. 53-56.
ISSN
0289-6605
CODEN
DOGIEL

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
25061190
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
CATALYSTS; CHEMICAL REACTION KINETICS; ELECTROLYSIS; MIXED OXIDE FUELS; NITRIC ACID; OXIDATION; PLUTONIUM DIOXIDE; REPROCESSING; SILVER NITRATES; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; ENERGY SOURCES; FUELS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; KINETICS; MATERIALS; NITRATES; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTION KINETICS; REACTOR MATERIALS; SEPARATION PROCESSES; SILVER COMPOUNDS; SOLID FUELS; TRANSITION ELEMENT COMPOUNDS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES