Reprocessing yields and material throughput: HTGR recycle demonstration facility

Technical Report · Mon Aug 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/7213301· OSTI ID:7213301

Holder, N.; Abraham, L.

Recovery and reuse of residual U-235 and bred U-233 from the HTGR thorium-uranium fuel cycle will contribute significantly to HTGR fuel cycle economics and to uranium resource conservation. The Thorium Utilization National Program Plan for HTGR Fuel Recycle Development includes the demonstration, on a production scale, of reprocessing and refabrication processes in an HTGR Recycle Demonstration Facility (HRDF). This report addresses process yields and material throughput that may be typically expected in the reprocessing of highly enriched uranium fuels in the HRDF. Material flows will serve as guidance in conceptual design of the reprocessing portion of the HRDF. In addition, uranium loss projections, particle breakage limits, and decontamination factor requirements are identified to serve as guidance to the HTGR fuel reprocessing development program. (28 tables, 18 figs.)

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• OSTI ID: 7213301
• Report Number(s): GA-A-14320
• Country of Publication: United States
• Language: English

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
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
DEMONSTRATION PLANTS
ELEMENTS
EVEN-ODD NUCLEI
FUEL CYCLE
FUEL ELEMENTS
FUEL REPROCESSING PLANTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAVY NUCLEI
HTGR TYPE REACTORS
ISOTOPES
METALS
NUCLEAR FACILITIES
NUCLEI
PERFORMANCE
PUREX PROCESS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
REPROCESSING
SEPARATION PROCESSES
SPENT FUEL ELEMENTS
THOREX PROCESS
THORIUM
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES