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Corrosion mechanisms of low level vitrified radioactive waste in a loamy soil

Published online by Cambridge University Press:  17 March 2011

M.I. Ojovan ,
W.E. Lee ,
A.S. Barinov ,
N.V. Ojovan ,
I.V. Startceva ,
D.H. Bacon ,
B.P. Mcgrail  and
J.D. Vienna
M.I. Ojovan
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, UK
W.E. Lee
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, UK
A.S. Barinov
Affiliation:
Scientific and Industrial Association “Radon”, Moscow, Russia
N.V. Ojovan
Affiliation:
Scientific and Industrial Association “Radon”, Moscow, Russia
I.V. Startceva
Affiliation:
Scientific and Industrial Association “Radon”, Moscow, Russia
D.H. Bacon
Affiliation:
Pacific Northwest National Laboratory, Richland, Washington, US
B.P. Mcgrail
Affiliation:
Pacific Northwest National Laboratory, Richland, Washington, US
J.D. Vienna
Affiliation:
Pacific Northwest National Laboratory, Richland, Washington, US
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Abstract

Field experiments have run for over 14 years to evaluate the behaviour of the same high-sodium content radioactive waste borosilicate glass buried in a loamy soil (glass K-26) and in an open testing area (glass Bs-10). Processing of field data for glass Bs-10 tested in an open area has resulted in a dissolution rate r = 0.42 µm/y and caesium diffusion coefficient D ≍ 1.8 10−20 m2/s at testing temperatures up to 19 oC. Both ion-exchange and hydrolysis control the corrosion of this glass. Processing of field data for K-26 glass revealed an insignificant role of glass dissolution. The caesium diffusion coefficient was estimated as D ≍ (3.4-5.1) 10−21 m2/s. Due to the relatively low storage temperatures (4.5 oC) used the leaching behaviour of glass K-26 is believed to be controlled by ion exchange processes. This mechanism is likely to remain dominant until the decay of 137Cs in the glass is below exemption levels.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC5.8
Copyright
Copyright © Materials Research Society 2004

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