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Title: Recovery of transplutonium elements from nuclear reactor waste

Abstract

A method of separating actinide values from nitric acid waste solutions resulting from reprocessing of irradiated nuclear fuels comprises oxalate precipitation of the major portion of actinide and lanthanide values to provide a trivalent fraction suitable for subsequent actinide/lanthanide partition, exchange of actinide and lanthanide values in the supernate onto a suitable cation exchange resin to provide an intermediate-lived raffinate waste stream substantially free of actinides, and elution of the actinide values from the exchange resin. The eluate is then used to dissolve the trivalent oxalate fraction prior to actinide/lanthanide partition or may be combined with the reprocessing waste stream and recycled.

Inventors:
 [1];  [2]
  1. Oak Ridge, TN
  2. Wartburg, TN
Issue Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OSTI Identifier:
862837
Patent Number(s):
4025602
Assignee:
United States of America as represented by United States Energy (Washington, DC)
Patent Classifications (CPCs):
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
recovery; transplutonium; elements; nuclear; reactor; waste; method; separating; actinide; values; nitric; acid; solutions; resulting; reprocessing; irradiated; fuels; comprises; oxalate; precipitation; major; portion; lanthanide; provide; trivalent; fraction; suitable; subsequent; partition; exchange; supernate; cation; resin; intermediate-lived; raffinate; stream; substantially; free; actinides; elution; eluate; dissolve; prior; combined; recycled; reprocessing waste; acid waste; lanthanide values; nuclear fuels; actinide values; irradiated nuclear; cation exchange; substantially free; waste stream; exchange resin; nitric acid; nuclear fuel; nuclear reactor; waste solutions; major portion; waste solution; reactor waste; solutions resulting; separating actinide; transplutonium element; processing waste; /423/976/

Citation Formats

Campbell, David O, and Buxton, Samuel R. Recovery of transplutonium elements from nuclear reactor waste. United States: N. p., 1977. Web.
Campbell, David O, & Buxton, Samuel R. Recovery of transplutonium elements from nuclear reactor waste. United States.
Campbell, David O, and Buxton, Samuel R. Tue . "Recovery of transplutonium elements from nuclear reactor waste". United States. https://www.osti.gov/servlets/purl/862837.
@article{osti_862837,
title = {Recovery of transplutonium elements from nuclear reactor waste},
author = {Campbell, David O and Buxton, Samuel R},
abstractNote = {A method of separating actinide values from nitric acid waste solutions resulting from reprocessing of irradiated nuclear fuels comprises oxalate precipitation of the major portion of actinide and lanthanide values to provide a trivalent fraction suitable for subsequent actinide/lanthanide partition, exchange of actinide and lanthanide values in the supernate onto a suitable cation exchange resin to provide an intermediate-lived raffinate waste stream substantially free of actinides, and elution of the actinide values from the exchange resin. The eluate is then used to dissolve the trivalent oxalate fraction prior to actinide/lanthanide partition or may be combined with the reprocessing waste stream and recycled.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1977},
month = {5}
}

Patent:

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