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Title: Process for recovering actinide values

Abstract

A process for rendering actinide values recoverable from sodium carbonate scrub waste solutions containing these and other values along with organic compounds resulting from the radiolytic and hydrolytic degradation of neutral organophosphorous extractants such as tri-n butyl phosphate (TBP) and dihexyl-N,N-diethyl carbamylmethylene phosphonate (DHDECAMP) which have been used in the reprocessing of irradiated nuclear reactor fuels. The scrub waste solution is preferably made acidic with mineral acid, to form a feed solution which is then contacted with a water-immiscible, highly polar organic extractant which selectively extracts the degradation products from the feed solution. The feed solution can then be processed to recover the actinides for storage or recycled back into the high-level waste process stream. The extractant is recycled after stripping the degradation products with a neutral sodium carbonate solution.

Inventors:
 [1];  [2]
  1. (Elmhurst, IL)
  2. (Clarendon Hills, IL)
Issue Date:
Research Org.:
Argonne National Laboratory (ANL), Argonne, IL
OSTI Identifier:
863596
Patent Number(s):
4208377
Assignee:
United States of America as represented by United States (Washington, DC) ANL
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
process; recovering; actinide; values; rendering; recoverable; sodium; carbonate; scrub; waste; solutions; containing; organic; compounds; resulting; radiolytic; hydrolytic; degradation; neutral; organophosphorous; extractants; tri-n; butyl; phosphate; tbp; dihexyl-n; n-diethyl; carbamylmethylene; phosphonate; dhdecamp; reprocessing; irradiated; nuclear; reactor; fuels; solution; preferably; acidic; mineral; acid; form; feed; contacted; water-immiscible; highly; polar; extractant; selectively; extracts; products; processed; recover; actinides; storage; recycled; high-level; stream; stripping; mineral acid; polar organic; actinide values; irradiated nuclear; feed solution; sodium carbonate; organic compound; process stream; organic compounds; nuclear reactor; waste solutions; reactor fuel; solutions containing; waste solution; carbonate solution; organic extractant; degradation products; selectively extracts; level waste; reactor fuels; selectively extract; recovering actinide; organophosphorous extractants; waste process; high-level waste; highly polar; organophosphorous extractant; compounds result; /423/976/

Citation Formats

Horwitz, E. Philip, and Mason, George W. Process for recovering actinide values. United States: N. p., 1980. Web.
Horwitz, E. Philip, & Mason, George W. Process for recovering actinide values. United States.
Horwitz, E. Philip, and Mason, George W. Tue . "Process for recovering actinide values". United States. https://www.osti.gov/servlets/purl/863596.
@article{osti_863596,
title = {Process for recovering actinide values},
author = {Horwitz, E. Philip and Mason, George W.},
abstractNote = {A process for rendering actinide values recoverable from sodium carbonate scrub waste solutions containing these and other values along with organic compounds resulting from the radiolytic and hydrolytic degradation of neutral organophosphorous extractants such as tri-n butyl phosphate (TBP) and dihexyl-N,N-diethyl carbamylmethylene phosphonate (DHDECAMP) which have been used in the reprocessing of irradiated nuclear reactor fuels. The scrub waste solution is preferably made acidic with mineral acid, to form a feed solution which is then contacted with a water-immiscible, highly polar organic extractant which selectively extracts the degradation products from the feed solution. The feed solution can then be processed to recover the actinides for storage or recycled back into the high-level waste process stream. The extractant is recycled after stripping the degradation products with a neutral sodium carbonate solution.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {1}
}

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