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Characterization of Radionuclide Retaining Properties of Backfill Materials for Near Surface Repositories for Low and Intermediate Level Radioactive Wastes

Published online by Cambridge University Press:  23 January 2013

Elizaveta E. Ostashkina
Affiliation:
Scientific and Industrial Association “Radon”, 119121 Moscow, Russia, the 7-th Rostovsky Lane, 2/14
Galina A. Varlakova
Affiliation:
Joint Stock Company “A.A.Bochvar High-technological Research Institute of Inorganic Materials”, 123098, Moscow, Russia, the Rogov Str, 5a.
Zoya I. Golubeva
Affiliation:
Scientific and Industrial Association “Radon”, 119121 Moscow, Russia, the 7-th Rostovsky Lane, 2/14
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Abstract

The sand of glaciolacustrine origin is offered as a major component of the backfill in repositories for solid or solidified low and intermediate level waste (LILW). Clinoptilolite, hematite, and magnesium oxide are offered as additives for increasing of sorption. In this work was carried investigation of sorption properties of sand, clinoptilolite, hematite and magnesium oxide and mixtures of sand with these mineral additives.

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Articles
Copyright
Copyright © Materials Research Society 2013 

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References

REFERENCES

GOST Р 52037-2003. Near surface repositories for disposal of radioactive waste. General technical requirements. Edition of standards, (Moscow, 2003).Google Scholar
NP-069-06. Near surface disposal of radioactive waste. Safety requirements. Federal rules and regulations in the field of atomic energy, (Moscow, 2006).Google Scholar
IAEA-TECDOC-1255, International Atomic Energy Agency, Performance of engineered barrier materials in near surface disposal facilities for radioactive waste. Results of a coordinated research project, (IAEA. Vienna, 2001), p.56.Google Scholar
Karnland, O., Sanden, T. in Long Term Test of Buffer Material at Aspo Hard Rock Laboratory, Sweden, (Mater. Res. Symp. Proc. 608, 2000) pp. 173178.Google Scholar
Glasser, F.P. in Characterisation of the barrier performance of cements, (Mater. Res. Symp. Proc. 713, 2002) pp. 721732.Google Scholar
Varlakova, G.A., Barinov, A.S., Ostashkina, E.E., Golubeva, Z.I. in Selection of Backfill materials for near surface repository for low and intermediate Level Waste, (Migration′11, Beiging, China, 2011) pp. 233234.Google Scholar
Varlakova, G.A., Golubeva, Z.I., Roschagina, S.V. et al. . in Development of backfill mixtures for near surface repository for radioactive waste, (“Radiochemistry-2009Moscow, 2009) pp. 253254.Google Scholar
Varlakova, G.A., Ostashkina, E.E., Golubeva, Z.I.. et al. ., RU Patent No. 2101200 (17 December 2010).Google Scholar
Serebryakov, B.E., Ivanov, E.A., Shchukin, A.P., Atomic Energy, 100, 3, 220225 (2006).Google Scholar
Cantrell, K.J., Serne, R.J., Last, G.V. in Hanford Contaminant Distribution Coefficient Database and Users Guide, (PNNL-13895 Rev. 1, June 2003).CrossRefGoogle Scholar
Kuznetsov, V.A., Generalova, V.A., Radiochemistry, 42, 2, 154157 (2000).Google Scholar
Sabodina, M.N., Zakharova, E.V., Kalmykov, S.N. et al. ., Radiochemistry, 50, 1, 8186 (2008).CrossRefGoogle Scholar
Dmitriev, S.A., Barinov, A.S., Varlakova, G.A. et al. . in Distribution and migration of radionuclides in host rock surrounding a shallow ground of vitrified radioactive waste, (Migration′2005, Avignon, France, 2005) p. 201.Google Scholar
Gorbacheva, M.P., Kulyuhin, S.A., Radiochemistry, 51, 3, 251254 (2009).CrossRefGoogle Scholar
Krumhansl, J.L., Papenguth, H.W., Zhang, P.C. in Scientific Basis for Nuclear Waste Management XXIV, (Mater. Res. Symp. Proc. 608, 2000). pp. 155160.Google Scholar