Molten salt destruction process for mixed wastes [electronic resource].
- Published:
- Washington, D.C. : United States. Dept. of Energy, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- 6 pages : digital, PDF file
- Additional Creators:
- Lawrence Livermore National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- We are developing an advanced two-stage process for the treatment of mixed wastes, which contain both hazardous and radioactive components. The wastes, together with an oxidant gas, such as air, are injected into a bed of molten salt comprising a mixture of sodium-, potassium-, and lithium-carbonates, with a melting point of about 580°C. The organic constituents of the mixed waste are destroyed through the combined effect of pyrolysis and oxidation. Heteroatoms. such as chlorine, in the mixed waste form stable salts, such as sodium chloride, and are retained in the melt. The radioactive actinides in the mixed waste are also retained in the melt because of the combined action of wetting and partial dissolution. The original process, consists of a one-stage unit, operated at 900--1000°C. The advanced two-stage process has two stages, one for pyrolysis and one for oxidation. The pyrolysis stage is designed to operate at 700°C. The oxidation stage can be operated at a higher temperature, if necessary.
- Report Numbers:
- E 1.99:ucrl-jc--112666
E 1.99: conf-930873--21
conf-930873--21
ucrl-jc--112666 - Subject(s):
- Other Subject(s):
- Note:
- Published through SciTech Connect.
04/01/1993.
"ucrl-jc--112666"
" conf-930873--21"
"DE93018641"
2. international mixed waste symposium,Baltimore, MD (United States),17-20 Aug 1993.
Karlsen, C.E.; Wilder, J.G.; Upadhye, R.S. - Funding Information:
- W-7405-ENG-48
View MARC record | catkey: 14416342