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Solvent extraction in HTGR reprocessing. Interim development report II

Technical Report ·
DOI:https://doi.org/10.2172/6567661· OSTI ID:6567661
This report contains the findings of a continuing program for the testing and evaluation of both Acid-Thorex and Purex flowsheets in HTGR fuel reprocessing. The tests were conducted to extend earlier studies on the effects of solvent degradation, feed solids impact, and decontamination performance using tracer /sup 95/Zr. Experiments to date indicate that acceptable operation is attainable in the reprocessing of HTGR fuels through the use of tributyl phosphate (TBP) extractant and pulsed solvent extraction columns. A centrifugal contactor is acceptable for the extraction step of the Purex flowsheet.
Research Organization:
General Atomic Co., San Diego, CA (USA)
OSTI ID:
6567661
Report Number(s):
GA-A-15030
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
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210802 -- Nuclear Power Plants-- Economics-- Fuel Cycle
BUTYL PHOSPHATES
DIAGRAMS
ESTERS
EVALUATION
EXTRACTION
FLOWSHEETS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
PUREX PROCESS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SOLVENT EXTRACTION
TBP
THOREX PROCESS