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Study of thermal and radiation stability of the extractant based on CMPO in fluorinated sulfones

Published online by Cambridge University Press:  27 December 2016

S.V. Stefanovsky ,
I.V. Skvortsov ,
E.V. Belova  and
A.V. Rodin
S.V. Stefanovsky*
Affiliation:
A.N. Frumkin Institute of Physical Chemistry and Electrochemistry RAS, Moscow 119071, Russia
I.V. Skvortsov
Affiliation:
A.N. Frumkin Institute of Physical Chemistry and Electrochemistry RAS, Moscow 119071, Russia
E.V. Belova
Affiliation:
A.N. Frumkin Institute of Physical Chemistry and Electrochemistry RAS, Moscow 119071, Russia
A.V. Rodin
Affiliation:
A.N. Frumkin Institute of Physical Chemistry and Electrochemistry RAS, Moscow 119071, Russia Scientific and Engineering Centre for Nuclear and Radiation Safety, Moscow 107140, Russia
*
*(Email: [email protected])
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Abstract

The two-phase systems of pure diluent FS-13 – aqueous solution of 14 mol/L nitric acid and 0.02 mol/L solution of CMPO in diluent FS-13 – aqueous solution of 14 mol/L HNO3 were studied at autoclave temperatures 170 °C and 200 °C. The effect of pre-irradiation on the kinetics of thermolysis was determined. All samples were irradiated using an electron accelerator at a dose rate of 10 kGy/h up to absorbed doses of 0.1, 0.5 and 1 MGy. The parameters of heat and gas emissions were determined during thermolysis of the studied extraction system in a closed apparatus. It has been shown that the conditions required for the growth of autocatalytic oxidation are not created during heating of the two-phase systems in closed vessels even for the extraction systems contacted with 14 mol/l HNO3 for two weeks.

Keywords

electron irradiationnuclear materialswaste management
Type
Articles
Information
MRS Advances , Volume 2 , Issue 12: Scientific Basis for Nuclear Waste Management XL , 2017 , pp. 641 - 647
Copyright
Copyright © Materials Research Society 2016 

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References

REFERENCES

Esimantovski, V.M., Galkin, B.Y., Lazarev, L.N., Lyubtsev, R.I., Romanovskii, V.N., Shishkin, D.N., Dzekun, E.G., in: Waste Management—92 Proc. Tucson, AZ, USA, 1992) p. 801.Google Scholar
Chemical Separation Technologies and Related Methods of Nuclear Waste Management. Applications, Problems, and Research Needs (Springer Science+Business Media, Dordrecht, 1999).Google Scholar
Babain, V.A., in: Ion Exchange and Solvent Extraction (CRC Press, 2009) pp. 359–380.CrossRefGoogle Scholar
Myasoedov, B.F., Chmutova, M.K., Smirnov, I.V., Shadrin, A.Y., in: Global’93 Conf. (Seattle WA, 1993).Google Scholar
Chmutova, M.K., Kochetkova, N.E., Myasoedov, B.F., J. Inorg. Nucl. Chem. 42, 897 (1980).Google Scholar
Medved’, T.Y., Chmutova, M.K., Nesterova, N.P., Koiro, O.E., Kochetkova, N.E., Myasoedov, B.F., Kabachnik, M.I.. Bull. Acad. Sci. USSR, 30, 1743 (1981).Google Scholar
Chmutova, M.K., Kochetkova, N.E., Myasoedov, B.F., Radiochem. 5, 713 (1978).Google Scholar
Romanovskiy, V.N., Smirnov, I.V., Babain, V.A., Todd, T.A., Herbst, R.S., Law, J.D., Brewer, K.N., Solvent Extr. Ion Exch., 19, 1 (2001).Google Scholar
Law, J.D., Herbst, R.S., Todd, T.A., Romanovskiy, V.N., Babain, V.A., Esimantovskiy, V.M., Smirnov, I.V., Zaitsev, B.N., Solvent Extr. Ion Exch., 19, 23 (2001).CrossRefGoogle Scholar
Herbst, R.S., Law, J.D., Todd, T.A., Romanovskiy, V.N., Babain, V.A., Esimantovskiy, V.M., Smirnov, I.V., Zaitsev, B.N., Solvent Extr. Ion Exch., 20, 429 (2002).Google Scholar
Herbst, R.S., Law, J.D., Todd, T.A., Romanovskiy, V.N., Smirnov, I.V., Babain, V.A., Esimantovskiy, V.N., Zaitsev, B.N., Sep. Sci. Technol., 38, 2685 (2003).Google Scholar
Herbst, R.S., Luther, T.A., Peterman, D.R., Babain, V.A., Smirnov, I.V., Stoyanov, E.S., in: Nuclear Waste Management (Amer. Chem. Soc. 2006) pp. 171–185.Google Scholar
Luther, T.A., Herbst, R.S., Peterman, D.R., Tillotson, R.D., Garn, T.G., Babain, V.A., Smirnov, I.V., Stoyanov, E.S., Antonov, N.G., Radioanal, J.. Nucl. Chem., 267, 603 (2006).Google Scholar
Sinha, P.K., Kumar, S., Kamachi Mudali, U., Natarajan, R., Radioanal, J.. Nucl. Chem., 289, 899 (2011).Google Scholar
Kumar, S., Muthukumar, M., Sinha, P.K., Mudali, U.K., Natarajan, R., J. Radioanal. Nucl. Chem., 289, 247 (2011).Google Scholar
Halleröd, J., Ekberg, C., Foreman, M., Engdahl, E.L., Aneheim, E., Radioanal, J.. Nucl. Chem., 304, 287 (2014).Google Scholar
Romanovsky, V.N.. Extraction Technology of Recovery of Long-Lived Radionuclides from Liquid High Level Waste by Application of Individual Phosphorus-Organic Compounds and Their Synergetic Mixtures. Diss. Dr. Sci. Tech. (SPb, Russia, 2001).Google Scholar
Mincher, B.J., Herbst, R.S., Tillotson, R.D., Mezyk, S.P., Solvent Extr. Ion Exch., 25, 747 (2007).Google Scholar
Nazin, E.R., Zachinyaev, G.M., Fire and Explosion Safety of Technological Processes in Radiochemical Industry. (Russ. M.: STC NRS, 2009).Google Scholar