Next-Generation Low-Carbon Cement Wasteforms for Safe Disposal of Radioactive Waste

用于安全处置放射性废物的下一代低碳水泥废料

• 批准号: 2735210
• 金额: --
• 依托单位: University of Sheffield
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2022
• 资助国家: 英国
• 起止时间: 2022 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2735210
• 关键词: Next; Generation; Low; Carbon; Cement

In the UK, over 150,000m3 of radioactive waste (enough to fill 60 Olympic size swimming pools) has been produced to date. Most of this radioactive waste needs conditioning by encapsulating it in cement to prevent release to the biosphere.Encapsulants based on Portland cement (PC) blended with supplementary cementitious materials (SCM) such as fly ash (FA) and blast furnace slag (BFS) are essential to cementation of much of the radioactive waste produced in the UK to date. However, with traditional SCM such as fly ash and blast furnace slag becoming increasingly scarce, development of PC/SCM encapsulants produced using abundant and readily available SCM such as limestone, calcined clays, and legacy slags, etc., is critical to ensure security of supply.There is currently limited information on what parameters of raw materials are critical to reliable application, particularly when these encapsulants are formulated with abundant SCM alternatives such as limestone, calcined clays, and legacy slags, under conditions required on nuclear encapsulation plants.This proposal investigates the mechanisms of fluid-particle and particle-particle interactions in PC/SCM encapsulants produced using limestone, calcined clays, and legacy slags as more abundant replacements for BFS and PFA,and the effect of this replacement on composition-structure-property relationships, and reaction mechanisms and kinetics.Through investigating fundamental particle interactions more robust specifications can be developed for precursor powders utilising abundant SCMs, ensuring security of supply.

在英国，迄今为止已经产生了超过150，000立方米的放射性废物（足以填满60个奥林匹克游泳池）。大多数放射性废物需要通过将其封装在水泥中进行调节，以防止释放到生物圈中。基于波特兰水泥（PC）与辅助胶凝材料（SCM）（如粉煤灰（FA）和高炉矿渣（BFS））混合的封装剂对于英国迄今为止产生的大部分放射性废物的胶凝至关重要。然而，随着传统SCM如粉煤灰和高炉矿渣变得日益稀缺，使用丰富且容易获得的SCM如石灰石、煅烧粘土和遗留矿渣等生产的PC/SCM澄清剂的开发，对于确保供应安全至关重要。目前关于原料的哪些参数对可靠应用至关重要的信息有限，特别是当这些澄清剂与大量SCM替代品（如石灰石、煅烧粘土和遗留炉渣）一起配制时，本论文研究了在核反应堆中流体-颗粒和颗粒-颗粒相互作用的机理。使用石灰石、煅烧粘土和传统矿渣生产的SCM澄清剂作为BFS和PFA的更丰富的替代品，以及这种替代对组成-结构-性能关系、反应机理和动力学的影响。通过研究基本粒子相互作用，可以为使用丰富SCM的前驱体粉末开发更稳健的规格，确保供应安全。