Molten salt processing of mixed wastes with offgas condensation
Creators
- 1. Lawrence Livermore National Lab., CA (USA)
- 2. Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group
Description
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
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91013518; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- UCRL-JC--107288
Conference
- Title
- environmental concerns and controls.
- Acronym
- 10. annual international incineration conference
- Dates
- 13-17 May 1991.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22086108
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALPHA-BEARING WASTES; DECOMPOSITION; DISSOLUTION; ENCAPSULATION; FEASIBILITY STUDIES; GASEOUS WASTES; HAZARDOUS MATERIALS; MOLTEN SALTS; OFF-GAS SYSTEMS; OXIDATION; PLUTONIUM OXIDES; PLUTONIUM 239; POLONIUM 218; PYROLYSIS; RADIOACTIVE WASTES; SOLVATION; STORAGE; URANIUM OXIDES; VERY HIGH TEMPERATURE; WASTE PROCESSING
- Descriptors DEC
- ACTINIDE COMPOUNDS; 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; RADIOACTIVE MATERIALS; RADIOISOTOPES; SALTS; SPONTANEOUS FISSION RADIOISOTO; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; WASTE MANAGEMENT; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-48
- Funding organization
- USDOE, Washington, DC (USA).
- Secondary number(s)
- CONF-910559--5.