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Title: Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides

Abstract

Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.

Inventors:
 [1]
  1. (Oak Ridge, TN)
Issue Date:
Research Org.:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
OSTI Identifier:
864651
Patent Number(s):
4397778
Assignee:
Lloyd, Milton H. (Oak Ridge, TN) ORNL
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
coprocessed; nuclear; fuels; containing; values; oxides; carbides; carbonitrides; method; direct; coprocessing; derived; product; stream; reprocessing; facility; uranium; plutonium; fission; comprising; nitrate; stabilization; vacuum; concentration; remove; water; nitrates; neutralization; form; acid; deficient; feed; solution; internal; gelation; mode; sol-gel; technology; green; spherule; formation; recovery; treatment; loading; fuel; element; vibra; packed; pellet; technologies; fuels containing; nuclear fuels; feed solution; fission product; product stream; fuel element; nuclear fuel; remove water; product values; containing uranium; internal gelation; pellet form; move water; /252/976/

Citation Formats

Lloyd, Milton H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides. United States: N. p., 1983. Web.
Lloyd, Milton H. Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides. United States.
Lloyd, Milton H. Sat . "Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides". United States. https://www.osti.gov/servlets/purl/864651.
@article{osti_864651,
title = {Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides},
author = {Lloyd, Milton H.},
abstractNote = {Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate stabilization of said stream vacuum concentration to remove water and nitrates, neutralization to form an acid deficient feed solution for the internal gelation mode of sol-gel technology, green spherule formation, recovery and treatment for loading into a fuel element by vibra packed or pellet formation technologies.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {1}
}

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