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Title: Plutonium recovery from spent direct oxide reduction salts by chloride anion exchange

Abstract

Chloride anion exchange has been investigated for recovery of plutonium from Direct Oxide Reduction (DOR) waste salts. Limited experimental results indicate that the conditions for <10/sup -3/ g/l losses of plutonium to effluents are feed adjustment to >8.5M total chloride, including 1.0M HC1 + 0.05M NaNO/sub 2/; a wash solution of 8M HC1 + 0.05M NaNO/sub 2/; elution with 0.5M HC1 and use of Amberlite IRA-938 for the anion exchange resin. These conditions result in >99% recovery of the plutonium. The eluate also contains approx.200 ppM calcium. Oxalic acid precipitation of Pu(III) recovers 99.2% if the molar ratio is 6:1 and the acidity is 0.8M. After calcination, the resulting plutonium oxide is suitable for DOR recycle if blended. Also, in the investigation, limited studies of extraction chromatography showed unacceptable plutonium losses to effluents.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Rockwell International Corp., Golden, CO (USA). Rocky Flats Plant
OSTI Identifier:
5948328
Report Number(s):
RFP-3945
ON: DE88002475
DOE Contract Number:  
AC04-76DP03533
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; PLUTONIUM; RECOVERY; ANIONS; EXTRACTION CHROMATOGRAPHY; ION EXCHANGE; OXALIC ACID; OXIDES; PRECIPITATION; REDUCTION; SALTS; WASTE PROCESSING; ACTINIDES; CARBOXYLIC ACIDS; CHALCOGENIDES; CHARGED PARTICLES; CHEMICAL REACTIONS; CHROMATOGRAPHY; DICARBOXYLIC ACIDS; ELEMENTS; IONS; MANAGEMENT; METALS; ORGANIC ACIDS; ORGANIC COMPOUNDS; OXYGEN COMPOUNDS; PROCESSING; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Muscatello, A C, Fisher, D C, Kazanjian, A R, Navratil, J D, and Stevens, J R. Plutonium recovery from spent direct oxide reduction salts by chloride anion exchange. United States: N. p., 1987. Web.
Muscatello, A C, Fisher, D C, Kazanjian, A R, Navratil, J D, & Stevens, J R. Plutonium recovery from spent direct oxide reduction salts by chloride anion exchange. United States.
Muscatello, A C, Fisher, D C, Kazanjian, A R, Navratil, J D, and Stevens, J R. 1987. "Plutonium recovery from spent direct oxide reduction salts by chloride anion exchange". United States.
@article{osti_5948328,
title = {Plutonium recovery from spent direct oxide reduction salts by chloride anion exchange},
author = {Muscatello, A C and Fisher, D C and Kazanjian, A R and Navratil, J D and Stevens, J R},
abstractNote = {Chloride anion exchange has been investigated for recovery of plutonium from Direct Oxide Reduction (DOR) waste salts. Limited experimental results indicate that the conditions for <10/sup -3/ g/l losses of plutonium to effluents are feed adjustment to >8.5M total chloride, including 1.0M HC1 + 0.05M NaNO/sub 2/; a wash solution of 8M HC1 + 0.05M NaNO/sub 2/; elution with 0.5M HC1 and use of Amberlite IRA-938 for the anion exchange resin. These conditions result in >99% recovery of the plutonium. The eluate also contains approx.200 ppM calcium. Oxalic acid precipitation of Pu(III) recovers 99.2% if the molar ratio is 6:1 and the acidity is 0.8M. After calcination, the resulting plutonium oxide is suitable for DOR recycle if blended. Also, in the investigation, limited studies of extraction chromatography showed unacceptable plutonium losses to effluents.},
doi = {},
url = {https://www.osti.gov/biblio/5948328}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {7}
}

Technical Report:
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