Coprocessing solvent-extraction flowsheet studies for LWR and FBR fuels

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:5367406

Collins, E D; Benker, D E; Bigelow, J E; Chattin, F R; King, L J; Lloyd, M H; Ross, R G; Stacy, R G; Savage, H C

Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need for an efficient feed clarification. A potentially useful filtration method for fulfilling this need has been demonstrated. Conditions necessary for the satisfactory use of unstabilized hydroxylamine nitrate (HAN) or nitrous acid as the reducing agent for Pu(IV) during reductive stripping operations have been defined. Both partial partitioning and total costripping operations have been demonstrated. In addition, solvent degradation product measurements have been made, and the effect of the presence of DBP during uranium-plutonium stripping operations has been determined.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5367406
• Report Number(s): CONF-820420-2; ON: DE82013541
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
AMINES
BREEDER REACTORS
BUTYL PHOSPHATES
BWR TYPE REACTORS
CHEMICAL REACTIONS
DBP
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
ESTERS
EXTRACTION
FAST REACTORS
FBR TYPE REACTORS
FUELS
HYDRAZINE
HYDROGEN COMPOUNDS
HYDROXYLAMINE
INORGANIC ACIDS
MATERIALS
METALS
MODIFICATIONS
NITROGEN COMPOUNDS
NITROUS ACID
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PARTITION
PHOSPHORIC ACID ESTERS
PLUTONIUM
PUREX PROCESS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPENT FUELS
TEST FACILITIES
TRANSURANIUM ELEMENTS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS