Depending on the lifetime and level of radioactivity of radioactive wastes, different disposal facilities are considered. Though low‐ and intermediate‐level short‐lived waste can be disposed in surface disposal facilities, deep geological disposal is considered for high‐ and intermediate‐level long‐lived waste. In France and Belgium, long‐term disposal is studied in clay host rock media. For aluminum, the disposal concept is based on encapsulation of the waste in a cement‐based matrix. It is also well‐known that aluminum is prone to severe corrosion in sufficiently alkaline environments leading to possible hydrogen production. To ensure the safety of the disposal facilities and the integrity of the cement capsules, the amount of aluminum that is disposed in each waste package must be specified and is limited to mitigate the level of hydrogen production by aluminum corrosion. In the present study, the corrosion resistance of an aluminum alloy (grade EN‐AW‐5754/H111) in two different cement matrices was studied in different configurations at room temperature. In each case, the evolution of hydrogen production was monitored to address the corrosion rate variation versus time.

中文翻译：

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5754铝合金在水泥基模拟核废料处理条件下的腐蚀行为

根据放射性废物的寿命和放射性水平，考虑使用不同的处置设施。尽管可以在地表处置设施中处置中低水平的短寿命废物，但对于高中水平的长寿命废物，可以考虑进行深度地质处置。在法国和比利时，对粘土基质岩石介质中的长期处置进行了研究。对于铝，处置概念是基于将废物封装在水泥基基质中。众所周知，铝在足够碱性的环境中容易受到严重腐蚀，从而可能产生氢气。为了确保处置设施的安全和水泥胶囊的完整性，必须规定每个废物包装中所含铝的量，并加以限制，以减轻因铝腐蚀而产生的氢气量。在本研究中，在室温下以不同的配置研究了铝合金（EN‐AW‐5754 / H111级）在两种不同水泥基体中的耐腐蚀性。在每种情况下，都要监测制氢量，以解决腐蚀速率随时间变化的情况。