Hostname: page-component-586b7cd67f-rcrh6 Total loading time: 0 Render date: 2024-11-23T15:25:57.265Z Has data issue: false hasContentIssue false
  • English
  • Français

Porous Alumina Silicate Matrix Gubka for Solidification of 137Cs Strip Product

Published online by Cambridge University Press:  19 October 2011

Albert Aloy ,
Alexander Strelnikov  and
Vyacheslav Essimantovskiy
Albert Aloy
Affiliation:
[email protected], "V.G. Khlopin Radium Institute" (KRI), RosAtom, 2-nd Murinsky str., 28, Saint Petersburg, 194021, Russian Federation, +7 812 545 42 15, +7 812 545 42 15
Alexander Strelnikov
Affiliation:
[email protected], "V.G. Khlopin Radium Institute", 2nd Murinskiy str., 28, Saint Petersburg, 194021, Russian Federation
Vyacheslav Essimantovskiy
Affiliation:
[email protected], "V.G. Khlopin Radium Institute", 2nd Murinskiy str., 28, Saint Petersburg, 194021, Russian Federation
Get access

Abstract

Separated liquid highâlevel radioactive waste (HLW) fractions, in particular, about 100 l of 137Cs strip product with activity up to ∼ 100 Ci/l (3.7 TBq/l) have been produced during the development and testing of partitioning technology and temporary stored at “V.G. Khlopin Radium Institute” (SaintâPetersburg, Russia). The benchâscale experimental unit designed for operation in the hot cell was developed for 137Cs strip product solidification with using of alumina silicate porous inorganic material (PIM) called Gubka.

Conditions of saturation, drying and calcinations of the salts into Gubka pores were optimized and the operations under remote control regime were executed during tests with using of simulated strip product doped with 137Cs. The volume reduction coefficients were equal by a factor of 3.2â3.9 and 137Cs discharge into offâgas system was not detected. 137Cs leach rates from Gubka blocks after calcination at 800 °C were 1.0â1.5*10-3 g/m2*day.

Keywords

waste managementadditivesliquid
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN11-02
Copyright
Copyright © Materials Research Society 2007

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Essimantovskiy, V. M., Galkin, B.Ya., Lazarev, L. N.. Eds. Post, R. G. and Wacks, M. E., (Mater. Proc. Symp. on Waste Management, l, Tucson, Arizona, 1992), pp. 801–804.Google Scholar
2. Nardova, A. K., Filipov, E. A., Egorov, G. F., (Proc. International Topical meeting on Nuclear and Hazardous waste Management, 1996), pp. 2120–2122.Google Scholar
3. Nardova, A. K., Tumanova, O. S., (Proc. SPECTRUM'96, Seattle, Washington, August 18–23, 1996) pp. 2154–2160.Google Scholar
4. Macedo, P. B., Tran, D. C., Simmons, J. H., Saleh, M., et. al. Eds. Chikalla, T. D., Mendel, J. E., Technical Information Center, DOE (Mater. Proc. Conf. On Ceramics in Nuclear Waste Management 1979), pp. 321–326.Google Scholar
5. Lazarev, L. N., Kuznesov, Yu. V., Shashukov, E. A., et. al.,(Proc. of Int. Symp. on Treatment Radioactive Waste for Interim and Ultimate Storage, Ulrecht, Netherlands, July 21-25, 1982), IAEA, Vienna, 1983, pp.253–263.Google Scholar
6. Aloy, A. S., Anshits, A. G., Tretyakov, A. A., Knecht, D. A., Tranter, T. J.,. Macheret, Y.. (Mat. Res. Soc. Symp. Proc. MRS ?99, 608, 2000), pp.637–642.Google Scholar
7. Aloy, A. S., Knecht, D. A., Tranter, T. J., Anshits, A. G., et. al., (Mater. Proc. Waste Management Symp WM'01, 2001), pp.79–83.Google Scholar
8. Aloy, A. S., Koltsova, T. I., Sapozhnikova, N. V., Strelnikov, A. S., “Ultra Porous Glass Crystalline Matrices Gubka for Solidification of 137Cs Strip Product”, Proc. ICEMí05, September 4–8, 2005, Glasgow, Scotland.Google Scholar