Stabilization of Radioactive Salt-Containing Liquid and Sludge waste on the Ceramic Matrices
Vernadsky Institute of geochemistry and analytical chemistry, Frumkin Institute of physical chemistry and electrochemistry Russian Academy of sciences, PA “Mayak” and Argonne National Laboratory (ANL) has worked since 2003 on a number of waste treatment a
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Vernadsky Institute of geochemistry and analytical chemistry, Frumkin Institute of physical chemistry and electrochemistry Russian Academy of sciences, PA “Mayak” and Argonne National Laboratory (ANL) has worked since 2003 on a number of waste treatment applications for the Ceramicrete technology based on KMgPO4 compound invented and patented at ANL. These include low level inorganic residues at Rocky Flats, and also TRU level waste organics, aqueous solvents, acids, and salts at PA Mayak. The study showed that high level wastes (and low activity wastes derived therefrom) could be treated to meet the waste acceptance criteria (WAC) for the waste repository at Yucca Mountain in Nevada and the Hanford waste disposal facility in Washington. Also, an improvement has been identified that would lead to a new class of ceramic waste forms. Those studies were conducted on simulants of high level liquid and sludge streams that comprise the chemical and radiological constituents that have proven to be most challenging for vitrification and other treatment technologies. The simulants contained isotopic and chemical surrogates for the radionuclides. Russia shares with the U.S. similar wastes and interests in finding cost-effective, simple, reliable treatment methods. Vernadsky Institute and PA Mayak worked on the following purposes: (1) to demonstrate the currently developed treatment methods using high level waste simulants containing the actual radioisotopes; (2) to further develop the potential improved ceramic formulation; (3) to develop a pilot scale facility for high level waste treatment; (4) to treat actual wastes at the pilot facility. In general, the laboratory work will be conducted at the Vernadsky Institute and the pilot plant work will be conducted at the PA Mayak site. Ivan G. Tananaev Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, Moscow, Russia; Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Moscow, Russia, e-mail: [email protected]
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Testing of ceramicrete samples produced using improved process technique has been carried out. It has been shown that the proposed scheme of solution preparation permits reliable stabilization of such waste elements as Cs, Sr, Ce, Ni, Cr and I. Degrees of leaching of structure-forming matrix components varied within the range of 0.8%–1.0% for Mg; 5%–13% for PO4 3− ; and 18%–33% for K. Tests on leaching of structure-forming matrix components from Ceramicrete samples with surrogate intermediate sludge have shown their minimal leaching. Weight loss of these samples was only 7.5%. One should note, that phosphate neutralization (as a method of preliminary preparation of solutions) permitted to reduce weight loss for stream solutions almost two times from 20% to 11%. In general, it may be stated that application of phosphate neutralization, ionites for sorption of iodine, and nickel ferrocyanide for sorption of cesium allows effective stabilization of radionuclides and toxic el
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