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  4. The influence of radiation on confinement properties of nuclear waste glasses
 
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The influence of radiation on confinement properties of nuclear waste glasses
File(s)
STNI Vol 2020, article 8875723, 14 pp (2020).pdf (2.12 MB)
Published version
Author(s)
Malkovsky, Victor I
Yudintsev, Sergey V
Ojovan, Michael
Petrov, Vladislav A
Type
Journal Article
Abstract
Self-irradiation can affect durability of glasses used to immobilize high-level nuclear waste (HLW). The stability of glasses can also be indirectly affected by the radiolytic changes in contact water leading to decrease in its pH although this is unlikely to occur for disposal systems where the interaction of groundwater with glass is delayed to times when radiation dose rates are decreased to levels insignificant to cause such effects. Besides, interaction of the water influenced by radiation with other repository protective elements (container and bentonite) will suppress the radiolytic changes. Literature analysis shows practical absence or very weak effect of self-irradiation on structure and characteristics of borosilicate glasses with typical content of nuclear waste. Data for aluminophosphate glass used in Russia have showed that, after γ-irradiation with a dose of 6.2·107 Gy, the leaching rates of elements were decreased approximately twice relatively to pristine samples.
Date Issued
2020-08-01
Date Acceptance
2020-07-16
Citation
Science and Technology of Nuclear Installations, 2020, 2020
URI
http://hdl.handle.net/10044/1/87010
DOI
https://www.dx.doi.org/10.1155/2020/8875723
ISSN
1687-6075
Publisher
Hindawi Publishing Corporation
Journal / Book Title
Science and Technology of Nuclear Installations
Volume
2020
Copyright Statement
© 2020 Viktor I. Malkovsky et al. *is is an open access article distributed under the Creative Commons AttributionLicense, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work isproperly cited.
License URL
Attribution 4.0 International
Subjects
Science & Technology
Technology
Nuclear Science & Technology
HIGH-LEVEL-WASTE
ALKALI-BOROSILICATE GLASSES
LEACH RATES
ALPHA-DECAY
CORROSION
WATER
IMMOBILIZATION
VITRIFICATION
MECHANISMS
VAPOR
Publication Status
Published
Article Number
ARTN 8875723
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