腐蚀
缺氧水域
胶凝的
水泥
放射性废物
环境科学
材料科学
氢
冶金
废物管理
环境化学
工程类
化学
有机化学
作者
Nicholas A. Senior,Taylor Martino,Nikitas Diomidis,R. Gaggiano
标识
DOI:10.1002/maco.202313765
摘要
Abstract The long‐term disposal of low‐ and intermediate‐level radioactive waste is anticipated to involve the encapsulation of the material within a cementitious matrix before placement in a deep geological repository. After sealing, the waste repository will become anoxic and the corrosion of emplaced metals will result in the production of hydrogen gas. Knowledge of the rate at which this hydrogen is generated is valuable in that it permits the assessment of pressure build‐up within the repository. The corrosion behavior of mild steel has been monitored through the generation of hydrogen gas, under simulated repository conditions that mimic various stages of cement evolution. It was found that, when cement is used to encapsulate steel, the passage of several years is required for the steel and cement to reach a steady hydrogen production rate. Steel that is directly immersed in simulated cement pore water requires only months to stabilize. All measured steel uniform corrosion rates were significantly below 1 nm year −1 at 50°C, regardless of the test environment, after more than 4 years of exposure.
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