Molten salt processing of mixed wastes with offgas condensation

Conference · Mon May 13 00:00:00 EDT 1991

OSTI ID:5564582

Cooper, J F; Brummond, W; Celeste, J; Farmer, J; Hoenig, C; Krikorian, O H; Upadhye, R ^[1]; Gay, R L; Stewart, A; Yosim, S ^[2]

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1. Lawrence Livermore National Lab., CA (USA)
2. Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group

We are developing an advanced process for treatment of mixed wastes in molten salt media at temperatures of 700--1000{degrees}C. Waste destruction has been demonstrated in a single stage oxidation process, with destruction efficiencies above 99.9999% for many waste categories. The molten salt provides a heat transfer medium, prevents thermal surges, and functions as an in situ scrubber to transform the acid-gas forming components of the waste into neutral salts and immobilizes potentially fugitive materials by a combination of particle wetting, encapsulation and chemical dissolution and solvation. Because the offgas is collected and assayed before release, and wastes containing toxic and radioactive materials are treated while immobilized in a condensed phase, the process avoids the problems sometimes associated with incineration processes. We are studying a potentially improved modification of this process, which treats oxidizable wastes in two stages: pyrolysis followed by catalyzed molten salt oxidation of the pyrolysis gases at ca. 700{degrees}C. 15 refs., 5 figs., 1 tab.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5564582
• Report Number(s): UCRL-JC-107288; CONF-910559-5; ON: DE91013518
• Resource Relation: Conference: 10. annual international incineration conference: environmental concerns and controls, Knoxville, TN (USA), 13-17 May 1991
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
HAZARDOUS MATERIALS
WASTE PROCESSING
RADIOACTIVE WASTES
ALPHA-BEARING WASTES
DECOMPOSITION
DISSOLUTION
ENCAPSULATION
FEASIBILITY STUDIES
GASEOUS WASTES
MOLTEN SALTS
OFF-GAS SYSTEMS
OXIDATION
PLUTONIUM 239
PLUTONIUM OXIDES
POLONIUM 218
PYROLYSIS
SOLVATION
STORAGE
URANIUM OXIDES
VERY HIGH TEMPERATURE
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHALCOGENIDES
CHEMICAL REACTIONS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
MATERIALS
MINUTES LIVING RADIOISOTOPES
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM ISOTOPES
POLONIUM ISOTOPES
PROCESSING
RADIOACTIVE MATERIALS
RADIOISOTOPES
SALTS
THERMOCHEMICAL PROCESSES
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
WASTE MANAGEMENT
WASTES
YEARS LIVING RADIOISOTOPES
052001* - Nuclear Fuels- Waste Processing