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Corrosion of Carbon Steel Containers During Open Site Tests of Vitrified Radioactive Waste

Published online by Cambridge University Press:  10 February 2011

A.S. Barinov
Affiliation:
Scientific and Industrial Association “Radon” The 7-th Rostovsky Lane, 2/14 Moscow, 119121, Russia Tel. (095)248 1680, Fax (095)248 1941, E-mail: [email protected]
M.I. Ojovan
Affiliation:
Scientific and Industrial Association “Radon” The 7-th Rostovsky Lane, 2/14 Moscow, 119121, Russia Tel. (095)248 1680, Fax (095)248 1941, E-mail: [email protected]
N.V. Ojovan
Affiliation:
Scientific and Industrial Association “Radon” The 7-th Rostovsky Lane, 2/14 Moscow, 119121, Russia Tel. (095)248 1680, Fax (095)248 1941, E-mail: [email protected]
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Abstract

In the middle of 80-s the Moscow SIA “Radon” initiates a program on long term tests of vitrified intermediate level radioactive waste from nuclear power plants with different types'of reactors and with different composition of waste. Glass blocks were prepared and disposed for tests in experimental shallow ground repository and on open testing area. Borosilicate glass as matrix material is investigated in order to obtain data on real behaviour of glass [1]. The waste glass was poured in carbon steel rectangular containers therefore containers also were subjected to aqueous and atmospheric corrosion. Exposure conditions at testing site are varying depending on season. They can be described only as average parameters with some uncertainties.

Type
Research Article
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1 Barinov, A.S., Ojovan, M.I., Ojovan, N.V., Mater. Res. Soc. Symp. Proc., 412, 265270 (1996).Google Scholar
2 Lee, J.H., Atkins, J.E., Andrews, R.W., Mat. Res. Soc. Symp. Proc., 412, 571580 (1996).Google Scholar
3 Uhlig, H.H., Revie, R.W., Corrosion and corrosion control. An Introduction to Corrosion Science and Engineering, John Wiley & Sons, Inc., 1985.Google Scholar