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Title: Chloride anion exchange coprocessing for recovery of plutonium from pyrochemical residues and Cs sub 2 PuCl sub 6 filtrate

Abstract

Continuing studies of plutonium recovery from direct oxide reduction (DOR) and electrorefining (ER) pyrochemical process residues show that chloride anion exchange coprocessing is useful and effective. Coprocessing utilizes DOR residue salt as a reagent to supply the bulk of chloride ion needed for the chloride anion exchange process and to improve ER residue salt solubility. ER residue salt and ER scrapeout can be successfully treated, either alone or together, using coprocessing. In addition, chloride anion exchange at 2.0M acidity results in improved process performance by greatly reducing disproportionation of plutonium(IV), eliminating restrictions on oxidation time compared to operation at 1.0M acidity. Laboratory-scale experiments show that below-discard effluent plutonium losses are obtained. Resin capacity was 30 g Pu/{ell} or greater. Furthermore, it is feasible to perform chloride anion exchange recovery of plutonium from filtrate resulting from precipitation of dicesium hexachloroplutonate (Cs{sub 2}PuCl{sub 6}, an oxidant salt to be used in the molten salt extraction process) and integration of its preparation with recovery of DOR salts. 10 refs., 9 figs., 10 tabs.

Authors:
;
Publication Date:
Research Org.:
EG and G Rocky Flats, Inc., Golden, CO (USA)
Sponsoring Org.:
DOE/DP
OSTI Identifier:
6303236
Report Number(s):
RFP-4325
ON: DE91006612
DOE Contract Number:  
AC34-90DP62349
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ANIONS; ION EXCHANGE; OXIDES; REDUCTION; PLUTONIUM; PYROCHEMICAL REPROCESSING; CESIUM CHLORIDES; ELECTROREFINING; PLUTONIUM CHLORIDES; ACTINIDE COMPOUNDS; ACTINIDES; ALKALI METAL COMPOUNDS; CESIUM COMPOUNDS; CHALCOGENIDES; CHARGED PARTICLES; CHEMICAL REACTIONS; CHLORIDES; CHLORINE COMPOUNDS; ELECTROLYSIS; ELEMENTS; HALIDES; HALOGEN COMPOUNDS; IONS; LYSIS; METALS; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PROCESSING; REFINING; REPROCESSING; SEPARATION PROCESSES; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Muscatello, A C, and Killion, M E. Chloride anion exchange coprocessing for recovery of plutonium from pyrochemical residues and Cs sub 2 PuCl sub 6 filtrate. United States: N. p., 1990. Web. doi:10.2172/6303236.
Muscatello, A C, & Killion, M E. Chloride anion exchange coprocessing for recovery of plutonium from pyrochemical residues and Cs sub 2 PuCl sub 6 filtrate. United States. https://doi.org/10.2172/6303236
Muscatello, A C, and Killion, M E. 1990. "Chloride anion exchange coprocessing for recovery of plutonium from pyrochemical residues and Cs sub 2 PuCl sub 6 filtrate". United States. https://doi.org/10.2172/6303236. https://www.osti.gov/servlets/purl/6303236.
@article{osti_6303236,
title = {Chloride anion exchange coprocessing for recovery of plutonium from pyrochemical residues and Cs sub 2 PuCl sub 6 filtrate},
author = {Muscatello, A C and Killion, M E},
abstractNote = {Continuing studies of plutonium recovery from direct oxide reduction (DOR) and electrorefining (ER) pyrochemical process residues show that chloride anion exchange coprocessing is useful and effective. Coprocessing utilizes DOR residue salt as a reagent to supply the bulk of chloride ion needed for the chloride anion exchange process and to improve ER residue salt solubility. ER residue salt and ER scrapeout can be successfully treated, either alone or together, using coprocessing. In addition, chloride anion exchange at 2.0M acidity results in improved process performance by greatly reducing disproportionation of plutonium(IV), eliminating restrictions on oxidation time compared to operation at 1.0M acidity. Laboratory-scale experiments show that below-discard effluent plutonium losses are obtained. Resin capacity was 30 g Pu/{ell} or greater. Furthermore, it is feasible to perform chloride anion exchange recovery of plutonium from filtrate resulting from precipitation of dicesium hexachloroplutonate (Cs{sub 2}PuCl{sub 6}, an oxidant salt to be used in the molten salt extraction process) and integration of its preparation with recovery of DOR salts. 10 refs., 9 figs., 10 tabs.},
doi = {10.2172/6303236},
url = {https://www.osti.gov/biblio/6303236}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {12}
}