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New route for synthesis of Synroc-like ceramic using non-selective sorbent LHT-9

Published online by Cambridge University Press:  19 February 2018

B.Yu. Zubekhina ,
B.E. Burakov ,
Yu.Yu. Petrov ,
S.N. Britvin ,
V.F. Mararitsa ,
Yu.T. Demidov  and
M.S. Nickolsky
B.Yu. Zubekhina*
Affiliation:
V.G. Khlopin Radium Institute (KRI), 28, 2-nd Murinskiy Ave., St-Petersburg, 194021, Russia
B.E. Burakov
Affiliation:
V.G. Khlopin Radium Institute (KRI), 28, 2-nd Murinskiy Ave., St-Petersburg, 194021, Russia
Yu.Yu. Petrov
Affiliation:
V.G. Khlopin Radium Institute (KRI), 28, 2-nd Murinskiy Ave., St-Petersburg, 194021, Russia
S.N. Britvin
Affiliation:
Saint-Petersburg State University, 7/9, Universitetskaya Nab. St-Petersburg, 199034, Russia Nanomaterials Research Center, Kola Science Center, RAS, 14, Fersman St., Apatity, 184200, Russia
V.F. Mararitsa
Affiliation:
Socium Ltd., St-Petersburg, Russia
Yu.T. Demidov
Affiliation:
Socium Ltd., St-Petersburg, Russia
M.S. Nickolsky
Affiliation:
Institute of Geology of Ore Deposits, Petrography, Mineralogy, and Geochemistry RAS, 35, Staromonetniy per., Moscow, 119017, Russia A.N. Frumkin Institute of Physical Chemistry and Electrochemistry RAS, 31/4, Leninsky pr., Moscow, 119071, Russia
*
*(Email: redvillage11@gmail.com)
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Abstract:

Immobilization of bulk liquid high level radioactive waste (HLW) in Synroc ceramic is well-known reliable way for final isolation of dangerous long-lived radionuclides from biosphere. The alternative method of Synroc-like ceramic synthesis has been proposed. Radionuclide incorporation into crystalline titanate host-phases can be provided as a result of direct radionuclide sorption from liquid HLW using non-selective sorbent – layered hydrazinium titanate (LHT-9). Such an approach allows excluding expensive multi-stage procedure of precursor preparation. The precipitate obtained after sorption can be easily transformed into Synroc-like ceramic by cold pressing followed with sintering in air at 1000-1200°C. The highly radioactive samples of titanate ceramic loaded with real HLW have been synthesized and preliminary studied at KRI hot-cell facility. Chemical durability of this sample has been studied using static leach test in distilled water at 90°C and the leach rates for 154Eu, 241Am, 244Cm were (in g·m-2·day-1) from 2·10-4 to 5·10-3. Normalised 137Cs mass loss was 0.3 g·m-2 for 110 days at the same conditions.

Keywords

ceramicwaste managementcrystalline
Type
Articles
Information
MRS Advances , Volume 3 , Issue 20: Scientific Basis for Nuclear Waste Management XLI , 2018 , pp. 1111 - 1116
Copyright
Copyright © Materials Research Society 2018 

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References

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