Reprocessing flowsheet and material balance for MEU spent fuel

Technical Report · Sun Oct 01 00:00:00 EDT 1978

DOI:https://doi.org/10.2172/6406904· OSTI ID:6406904

Abraham, L

In response to nonproliferation concerns, the high-temperature gas-cooled reactor (HTGR) Fuel Recycle Development Program is investigating the processing requirements for a denatured medium-enriched uranium--thorium (MEU/Th) fuel cycle. Prior work emphasized the processing requirements for a high-enriched uranium--thorium (HEU/Th) fuel cycle. This report presents reprocessing flowsheets for an HTGR/MEU fuel recycle base case. Material balance data have been calculated for reprocessing of spent MEU and recycle fuels in the HTGR Recycle Reference Facility (HRRF). Flowsheet and mass flow effects in MEU-cycle reprocessing are discussed in comparison with prior HEU-cycle flowsheets.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: EY-76-C-03-0167-053
• OSTI ID: 6406904
• Report Number(s): GA-A-15145; TRN: 79-003933
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
HEAD END PROCESSES
MATERIAL BALANCE
OFF-GAS SYSTEMS
SPENT FUELS
THOREX PROCESS
FLOWSHEETS
HTGR TYPE REACTORS
MODERATELY ENRICHED URANIUM
REPROCESSING
THORIUM OXIDES
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
DIAGRAMS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
ISOTOPE ENRICHED MATERIALS
METALS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
REACTOR MATERIALS
REACTORS
SEPARATION PROCESSES
THORIUM COMPOUNDS
URANIUM
050800* - Nuclear Fuels- Spent Fuels Reprocessing