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

Patent · Sat Jan 01 04:00:00 EST 1983

OSTI ID:864651

Lloyd, Milton H ^[1]

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1. Oak Ridge, TN

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.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN
• Assignee: Lloyd, Milton H. (Oak Ridge, TN)
• Patent Number(s): US 4397778
• OSTI ID: 864651
• Country of Publication: United States
• Language: English

Related Subjects

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feed solution
fission
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sol-gel
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spherule
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technologies
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water