Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

被引:26
|
作者
Guo, Xiaolei [1 ]
Gin, Stephane [2 ]
Frankel, Gerald S. [1 ]
机构
[1] Ohio State Univ, Dept Mat Sci & Engn, 116 W 19Th Ave, Columbus, OH 43210 USA
[2] Univ Montpellier, CEA, DEN, ISEC,DE2D, F-30207 Marcoule, Bagnols Sur Cez, France
关键词
LONG-TERM BEHAVIOR; CARBON-STEEL; GLASS ALTERATION; LOCALIZED CORROSION; GEOLOGICAL DISPOSAL; BOROSILICATE GLASS; PITTING CORROSION; RADIOACTIVE-WASTE; STAINLESS-STEELS; IODINE RELEASE;
D O I
10.1038/s41529-020-00140-7
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This review covers the corrosion interactions between different materials that are relevant to the disposal of high-level nuclear waste, in particular the waste forms and containers. The materials of interest are borosilicate glass, crystalline ceramics, metal alloys, and any corrosion products that might form. The available data show that these interactions depend on the structure, chemistry, thermodynamic history, and proximity of the materials in contact, as well as the environmental attributes, such as temperature, solution chemistry, and radiation. Several key mechanisms that govern these interactions are highlighted. Scientific gaps and open questions are summarized and discussed.
引用
收藏
页数:16
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