Published August 9, 1983 | Version v1
Patent Metadata-only

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

Creators

Description

A method is disclosed 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

Availability note (English)

U.S. Commissioner of Patents, Washington, D.C. 20231, USA, $.50.

Additional details

Publishing Information

Imprint Pagination
v p.
IPC:
Int. Cl. G21C 19/46.
IPC
Int. Cl. G21C 19/46.
Patent number
US patent document 4,397,778/A/

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15024197
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
FUEL REPROCESSING PLANTS; PLUTONIUM CARBIDES; PLUTONIUM NITRIDES; PLUTONIUM OXIDES; REPROCESSING; SPENT FUEL ELEMENTS; SPENT FUELS; URANIUM CARBIDES; URANIUM NITRIDES; URANIUM OXIDES
Descriptors DEC
ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FUEL ELEMENTS; FUELS; MATERIALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FACILITIES; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR COMPONENTS; REACTOR MATERIALS; SEPARATION PROCESSES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS

Optional Information

Notes
PAT-APPL-223547.