Review of the Modelling of Corrosion Processes and Lifetime Prediction for HLW/SF Containers—Part 1: Process Models

Fraser King, Miroslav Kolàř, S. Briggs, M. Behazin, P. Keech, N. Diomidis
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Abstract

The disposal of high-level radioactive waste (HLW) and spent nuclear fuel (SF) presents a unique challenge for the prediction of the long-term performance of corrodible structures since HLW/SF containers are expected, in some cases, to have lifetimes of one million years or longer. Various empirical and deterministic models have been developed over the past 45 years for making predictions of long-term corrosion behaviour, including models for uniform and localised corrosion, environmentally assisted cracking, microbiologically influenced corrosion, and radiation-induced corrosion. More recently, fracture-mechanics-based approaches have been developed to account for joint mechanical–corrosion degradation modes. Regardless of whether empirical or deterministic models are used, it is essential to be able to demonstrate a thorough mechanistic understanding of the corrosion processes involved. In addition to process models focused on specific corrosion mechanisms, there is also a need for performance-assessment models as part of the overall demonstration of the safety of a deep geological repository. Performance-assessment models are discussed in Part 2 of this review.
高浓铀/低浓铀容器腐蚀过程建模和寿命预测回顾--第 1 部分:过程模型
高放射性废物(HLW)和乏核燃料(SF)的处置对可腐蚀结构的长期性能预测提出了独特的挑战,因为在某些情况下,HLW/SF 容器的寿命预计可达一百万年或更长。在过去的 45 年中,已经开发了各种经验模型和确定性模型来预测长期腐蚀行为,包括均匀腐蚀和局部腐蚀模型、环境辅助开裂模型、微生物影响腐蚀模型和辐射诱导腐蚀模型。最近,还开发了基于断裂力学的方法,用于解释机械-腐蚀联合降解模式。无论使用经验模型还是确定性模型,都必须能够证明对相关腐蚀过程有透彻的机械理解。除了侧重于特定腐蚀机制的过程模型外,还需要性能评估模型,作为深地质处置库安全性总体论证的一部分。本综述的第二部分将讨论性能评估模型。
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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CiteScore
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