TRUEX hot demonstration. Final report

Technical Report · Sun Apr 01 04:00:00 EDT 1990

DOI:https://doi.org/10.2172/10173771· OSTI ID:10173771

Chamberlain, D B; Leonard, R A; Hoh, J C; Gay, E C; Kalina, D G; Vandegrift, G F

In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10173771
• Report Number(s): ANL--89/37; ON: DE92040604
• Country of Publication: United States
• Language: English

Related Subjects

050800
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DEMONSTRATION PROGRAMS
DISSOLVERS
EXTRACTION
INERTIAL SEPARATORS
MATERIALS RECOVERY
PHOSPHINE OXIDES
PROGRESS REPORT
PUREX PROCESS
SPENT FUELS
SPENT FUELS REPROCESSING
TRANSURANIUM ELEMENTS
TRUEX PROCESS