Evolution in mechanical and microstructural properties of radioactive liquid organic waste-bearing alkali-activated slag under accelerated carbonation

IF 2.5 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2026-03-01 Epub Date: 2025-12-15 DOI:10.1016/j.nucengdes.2025.114682

Emile Mukiza , Thi Nhan Nguyen , Lander Frederickx , Quoc Tri Phung

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引用次数: 0

Abstract

This study examines the durability of alkali-activated slag (AAS) concerning carbonation resistance, incorporating Nevastane (NEV) and Shellspirax (SHE) as surrogates for radioactive liquid organic waste. The findings reveal that vaterite is the predominant CaCO₃ polymorph formed in the AAS-based specimens, regardless of the presence of oil. Furthermore, the mechanical strength of the AASs incorporating oil (waste forms) remains stable under carbonation conditions. The degree of carbonation of these waste forms is significantly influenced by the type of oil, waste loading, and water-to-binder (w/b) ratio. Notably, waste forms containing NEV exhibit superior carbonation resistance compared to those containing SHE. The encapsulation of oil within AAS matrices adversely affects the pore structure development, and exposure to accelerated carbonation further coarsens the microstructure. AAS matrices show potential for the immobilization of challenging radioactive liquid organic waste. Given the significant impact of oil type on carbonation extent, further testing with relevant radioactive liquid organic waste is necessary to ensure the durability of the waste form against carbonation before its application in real-world scenarios.

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含放射性液体有机废物碱活性渣在加速碳化作用下的力学和显微组织性能演变

本研究采用Nevastane （NEV）和Shellspirax （SHE）作为放射性液体有机废物的替代品，考察了碱活性渣（AAS）在抗碳化方面的耐久性。研究结果表明，无论是否存在石油，aas基样品中主要形成的CaCO3多晶型都是灰质岩。此外，在碳化条件下，含油（废形式）的AASs的机械强度保持稳定。这些废物形式的碳酸化程度受油的类型、废物装载量和水与粘合剂（w/b）比的显著影响。值得注意的是，与含有SHE的废物相比，含有新能源汽车的废物形式具有更好的抗碳化能力。油在AAS基体中的包封对孔隙结构的发育有不利影响，加速碳酸化进一步使微观结构变粗。原子吸收光谱基质显示了具有挑战性的放射性液体有机废物的固定化潜力。考虑到油类对碳酸化程度的显著影响，在实际应用之前，有必要用相关的放射性液体有机废物进行进一步的测试，以确保废物形式对碳酸化的耐久性。

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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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.