Accounting for engineered barrier saturation, steel container corrosion, hydrogen production and transfer within fractured rock in the assessments of low sorbing radionuclides release from geological disposal facilities

IF 2.1 Q3 ENGINEERING, ENVIRONMENTAL
S. Bogatov, V. V. Suskin
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引用次数: 0

Abstract

The paper discusses the influence of bentonite saturation, package failure and water conductive fracture network on the transport of long-lived low sorbing radionuclides in geological disposal facilities (DGR). Based on the example of 129I, the study evaluates the influence of space and time dispersion of radionuclide transport and processes mentioned above on the long-term DGR safety. It demonstrates that these effects can cause significant radionuclide retention, nevertheless having minor impact on the long-term DGR safety as regards low sorbing nuclides with their half-lives amounting to over hundreds of thousand years. The paper also considers the opportunities for enhancing the GDF safety considering such radionuclides.
在地质处置设施低吸收性放射性核素释放评估中,考虑工程屏障饱和、钢容器腐蚀、断裂岩石内氢气的产生和转移
本文讨论了膨润土饱和度、包封破坏和导水裂缝网络对地质处置设施中长寿命低吸收放射性核素运移的影响。以129I为例,评价核素输运的时空色散及上述过程对DGR长期安全性的影响。研究表明,这些影响可造成显著的放射性核素滞留,但对半衰期超过几十万年的低吸收核素的长期DGR安全影响不大。本文还讨论了在考虑这些放射性核素的情况下提高GDF安全性的机会。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
5.40
自引率
7.40%
发文量
80
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