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

Patent · Sat Jan 01 00:00:00 EST 1983

OSTI ID:864651

Lloyd, Milton H ^[1]

---

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

Related Subjects

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/