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Coprocessing solvent extraction flowsheet studies for LWR and FBR fuels

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6883264
; ; ; ; ; ; ; ;
None
Research Organization:
ORNL-U.S., Oak Ridge, TN 37830
OSTI ID:
6883264
Report Number(s):
CONF-820420-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 40
Country of Publication:
United States
Language:
English

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Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BREEDER REACTORS
BWR TYPE REACTORS
DIAGRAMS
ENERGY SOURCES
EPITHERMAL REACTORS
EXTRACTION
FAST REACTORS
FBR TYPE REACTORS
FLOWSHEETS
FUELS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPENT FUELS
TECHNOLOGY ASSESSMENT
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS