放射性废物处置条件下水泥基材料的吸附机制、长期演化及安全启示

    Sorption Mechanisms, Long-Term Evolution, and Safety Implications of Cement-Based Materials Under Radioactive Waste Disposal Conditions

    • 摘要: 水泥基材料是放射性废物处置库中工程屏障系统不可或缺的组成部分。它们在结构支撑、化学屏障和近场地球化学调控等方面发挥着多重关键作用,在“近地表-深地质”全谱系放射性废物处置中扮演不可替代的角色。本文全面综述了当前处置环境下水泥基材料行为的科学研究进展,特别强调了放射性核素的固定机制、水泥材料的长期降解过程以及其在多重屏障系统中的作用。水泥主要水化产物如硅酸(铝)钙(C-(A)-S-H)水化物、氢氧化钙、钙矾石(AFt)和层状双氢氧化物(AFm)相等,为阳离子和阴离子型放射性核素提供了丰富的吸附位点,其机制包括离子交换、表面配位和结构并入等。在水泥降解过程中,吸附行为还受到孔隙水pH值、氧化还原条件及其组成变化的影响。对于某些氧化还原敏感核素(如99Tc、79Se和235,238U),除像其他核素一样与AFm相、AFt、碳酸盐、沸石或降解硅铝酸盐等矿物发生反应外,也可在水泥-钢界面通过化学还原反应被阻滞。由纤维素降解生成的有机配体(如异糖酸(ISA))也会显著影响放射性核素的迁移,ISA可与锕系和镧系金属形成稳定的可溶配合物,显著降低其在水泥中的吸附效率。热力学模型、表面配位模型、反应运移模型以及热-水-力-化耦合模拟等对预测水泥的长期性能、支持处置库设计和构建监管框架具有重要意义。此外,与地下实验室的现场数据耦合、通过长期实验进行模型验证也是降低预测结果不确定性的关键措施,为处置库安全评价的可靠性提供关键保障。考虑到传统水泥(如普通硅酸盐水泥OPC)在高pH值、碳排放和与缓冲材料化学兼容性方面的局限,低pH水泥、地质聚合物、镁基胶凝材料等替代体系在环境友好性和与围岩/膨润土兼容性方面具有优势,但在长期耐久性、监管适应性以及放射性核素吸附数据方面仍需进一步研究。当水泥与膨润土缓冲材料、钢容器及围岩接触时,会形成复杂的界面区,表现出矿物转化、孔隙率变化及氧化还原条件转移等特征,深入理解这些界面区的演化过程对于预测多重屏障系统整体性能至关重要,本文总结了这些交互作用对放射性核素迁移行为的潜在影响。此外,还就水泥材料长期行为验证、热力学数据库完善、有机物及微生物过程模拟方法的发展、新型胶凝材料的标准化测试框架等方面做了展望。

       

      Abstract: Cement-based materials are indispensable components in the engineered barrier systems of repositories for radioactive waste. They fulfill multiple critical roles, including structural support, chemical containment, and geochemical conditioning of the near-field environment, and thus constitute an indispensable component across the entire “near-surface to deep-geological ” disposal spectrum. This review presents a comprehensive synthesis of current scientific understanding regarding the behavior of cementitious materials in repository conditions, with an emphasis on radionuclide immobilization mechanisms, long-term degradation processes, and integration within multi-barrier systems. Key cement hydration products such as calcium(alumino)silicate hydrate(C-(A)-S-H), portlandite, ettringite(AFt), and layered double hydroxide(AFm) phases provide abundant sorption sites for cationic and anionic radionuclides through ion exchange, surface complexation, and incorporation mechanisms. Sorption is further modulated by the evolving pH, redox conditions, and porewater composition during cement degradation. Redox-sensitive radionuclides such as 99Tc, 79Se, and 235,238U may be immobilized via reduction at steel-cement interfaces, while others interact with secondary phases such as carbonates, zeolites, or degraded aluminosilicates. A major focus is given to the influence of organic ligands, such as isosaccharinic acid(ISA), produced by cellulose degradation, and their strong ability to form soluble complexes with actinides and lanthanides. These interactions significantly reduce sorption efficiency, necessitating conservative treatment in safety assessments. The review also addresses advanced modeling strategies, including surface complexation models(SCMs), reactive transport modeling, and thermo-hydro-mechanical-chemical(THMC) simulations. These tools are essential for predicting long-term performance, supporting repository design, and informing regulatory frameworks. Integration with field data from underground research laboratories and validation through long-term experiments remain vital to reduce uncertainties. Alternative cement systems, such as low-pH cements, geopolymers, and magnesium-based binders, are explored as more sustainable and chemically compatible options for repository applications. While promising in terms of reduced pH and improved environmental profiles, these materials face challenges related to long-term durability, regulatory acceptance, and comprehensive radionuclide retention data. As cement interacts with bentonite buffers, steel containers, and host rocks, it generates complex interfacial zones characterized by mineral transformations, porosity changes, and redox shifts. Understanding these interfaces is crucial to predict the evolution of the multi-barrier system. The review synthesizes experimental insights and modeling approaches to capture these interactions and their implications for radionuclide transport. In conclusions, the paper outlines key challenges and research priorities, including validation of long-term behavior, refinement of thermodynamic databases, modeling of organics and microbial processes, and development of standardized protocols for new binders. By fostering interdisciplinary collaboration and integrating experimental, modeling, and regulatory perspectives, the scientific community can ensure that cementitious barriers remain reliable, adaptable, and effective components of safe radioactive waste isolation.

       

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