Solvent extraction in HTGR reprocessing. Interim development report

Technical Report · Sun Feb 01 00:00:00 EST 1976

DOI:https://doi.org/10.2172/7352058· OSTI ID:7352058

Reddick, G. W.

Acid-Thorex flowsheets using tributyl phosphate (TBP) to process feed which simulated that from HTGR fuels were tested in pulsed solvent extraction columns. Tests were performed to study the effects of solvent degradation and solids in the feed and decontamination performance using tracer Zr-95. Equipment recommendations for each process step are made. The Acid-Thorex process is expected to provide relatively trouble-free operation in commercial reprocessing of HTGR fuel. (auth)

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: E(04-3)-167
• OSTI ID: 7352058
• Report Number(s): GA-A-13835; TRN: 76-014207
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SPENT FUELS
THOREX PROCESS
RESEARCH PROGRAMS
THORIUM
SOLVENT EXTRACTION
URANIUM
DECOMPOSITION
DECONTAMINATION
EFFICIENCY
FLOWSHEETS
HTGR TYPE REACTORS
TBP
ACTINIDES
BUTYL PHOSPHATES
CHEMICAL REACTIONS
CLEANING
DIAGRAMS
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
METALS
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
REACTOR MATERIALS
REACTORS
REPROCESSING
SEPARATION PROCESSES
050800* - Nuclear Fuels- Spent Fuels Reprocessing
400105 - Separation Procedures
210802 - Nuclear Power Plants- Economics- Fuel Cycle