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:
-
- Oak Ridge, TN
- Issue Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- OSTI Identifier:
- 864651
- Patent Number(s):
- 4397778
- Assignee:
- Lloyd, Milton H. (Oak Ridge, TN)
- Patent Classifications (CPCs):
-
B - PERFORMING OPERATIONS B01 - PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL B01J - CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- 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 = {Sat Jan 01 00:00:00 EST 1983},
month = {Sat Jan 01 00:00:00 EST 1983}
}
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.