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Title: Actinide recovery from pyrochemical residues

Abstract

A new process for recovery of plutonium and americium from pyrochemical waste has been demonstrated. It is based on chloride solution anion exchange at low acidity, which eliminates corrosive HCl fumes. Developmental experiments of the process flowsheet concentrated on molten salt extraction (MSE) residues and gave >95% plutonium and >90% americium recovery. The recovered plutonium contained <500 ppM americium and <2500 ppM magnesium. The process operates by sorbing PuCl/sub 6/ = from high chloride-low acid solution. Americium and other metals are washed from the ion exchange column with 1N HNO/sub 3/-4.8M NaCl. The plutonium is recovered, after elution, via hydroxide precipitation, while the americium is recovered via NaHCO/sub 3/ precipitation. All filtrates from the process are discardable as low-level contaminated waste. Production-scale experiments are now in progress for MSE residues. Flow sheets for actinide recovery from electrorefining and direct oxide reduction residues are presented and discussed.

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (USA)
OSTI Identifier:
6255129
Report Number(s):
LA-UR-84-3809; CONF-841210-9
ON: DE85005725
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: International chemical congress of Pacific Basin Societies, Honolulu, HI, USA, 16 Dec 1984; Other Information: Portions are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; AMERICIUM; ION EXCHANGE; RECOVERY; PLUTONIUM; PRECIPITATION; ACTINIDES; ELEMENTS; METALS; SEPARATION PROCESSES; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; 400105* - Separation Procedures; 052001 - Nuclear Fuels- Waste Processing

Citation Formats

Avens, L R, Clifton, D G, and Vigil, A R. Actinide recovery from pyrochemical residues. United States: N. p., 1984. Web.
Avens, L R, Clifton, D G, & Vigil, A R. Actinide recovery from pyrochemical residues. United States.
Avens, L R, Clifton, D G, and Vigil, A R. 1984. "Actinide recovery from pyrochemical residues". United States.
@article{osti_6255129,
title = {Actinide recovery from pyrochemical residues},
author = {Avens, L R and Clifton, D G and Vigil, A R},
abstractNote = {A new process for recovery of plutonium and americium from pyrochemical waste has been demonstrated. It is based on chloride solution anion exchange at low acidity, which eliminates corrosive HCl fumes. Developmental experiments of the process flowsheet concentrated on molten salt extraction (MSE) residues and gave >95% plutonium and >90% americium recovery. The recovered plutonium contained <500 ppM americium and <2500 ppM magnesium. The process operates by sorbing PuCl/sub 6/ = from high chloride-low acid solution. Americium and other metals are washed from the ion exchange column with 1N HNO/sub 3/-4.8M NaCl. The plutonium is recovered, after elution, via hydroxide precipitation, while the americium is recovered via NaHCO/sub 3/ precipitation. All filtrates from the process are discardable as low-level contaminated waste. Production-scale experiments are now in progress for MSE residues. Flow sheets for actinide recovery from electrorefining and direct oxide reduction residues are presented and discussed.},
doi = {},
url = {https://www.osti.gov/biblio/6255129}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1984},
month = {1}
}

Conference:
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