Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries
Patent
·
OSTI ID:867005
- Elkton, MD
- Augusta, GA
A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper (II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the orginal organic compounds, is subsequently blended with high level radioactive sludge and transferred to a virtrification facility for processing into borosilicate glass for long-term storage.
- Research Organization:
- E I DUPONT DE NEMOURS & CO INC
- DOE Contract Number:
- AC09-76SR00001
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 4840765
- OSTI ID:
- 867005
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
precipitate
hydrolysis
process
removal
organic
compounds
nuclear
waste
slurries
removing
slurry
comprising
reacting
mixture
radioactive
acid
presence
catalytically
effective
amount
copper
ii
catalyst
whereby
hydrolyzed
form
volatile
separated
resulting
containing
10
percent
orginal
subsequently
blended
level
sludge
transferred
virtrification
facility
processing
borosilicate
glass
long-term
storage
term storage
comprising reacting
catalytically effective
form volatile
slurry comprising
effective amount
organic compound
organic compounds
radioactive waste
nuclear waste
volatile organic
long-term storage
silicate glass
level radioactive
removing organic
reacting mixture
waste slurry
hydrolysis process
borosilicate glass
/376/210/423/976/
hydrolysis
process
removal
organic
compounds
nuclear
waste
slurries
removing
slurry
comprising
reacting
mixture
radioactive
acid
presence
catalytically
effective
amount
copper
ii
catalyst
whereby
hydrolyzed
form
volatile
separated
resulting
containing
10
percent
orginal
subsequently
blended
level
sludge
transferred
virtrification
facility
processing
borosilicate
glass
long-term
storage
term storage
comprising reacting
catalytically effective
form volatile
slurry comprising
effective amount
organic compound
organic compounds
radioactive waste
nuclear waste
volatile organic
long-term storage
silicate glass
level radioactive
removing organic
reacting mixture
waste slurry
hydrolysis process
borosilicate glass
/376/210/423/976/