Decontamination of carbonaceous nuclear waste streams for segregation and possible re-use

对碳质核废物流进行净化以进行分离和可能的再利用

• 批准号: 2747184
• 金额: --
• 依托单位: University of Manchester
• 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-2747184
• 关键词: Decontamination; carbonaceous; nuclear; waste; streams

This project aims to develop an efficient and cost-effective approach for managing carbonaceous nuclear waste streams, including nuclear graphite as it is one of the most critical aspects of any proposed decommissioning strategy for both existing and proposed new-generation nuclear reactor systems (e.g. High Temperature Gas Reactors {HTGRs}) which use graphite as a moderator, reflector or structural material. We have recently developed a patented molten salt decontamination method that will segregate the majority of the radioactive constituents in contaminated graphite decreasing the volume of intermediate level waste requiring geological disposal. This method can be developed further to allow the potential reuse of the remaining decontaminated intact graphite matrix, further reducing waste stream volumes and interim storage needs. This project aims to develop this novel approach for graphite reuse and assess its applicability for treatment of a variety of carbonaceous waste streams, identified as an area of interest across the Nuclear Decommissioning Authoirty (NDA) estate on Sorting & Segregation & Minimising Waste Volumes including the compaction or repurposing/reuse of graphite. Work will therefore focus on developing methods for scaling up this decontamination approach with a comprehensive assessment of the waste streams, including the feasibility for re-using the decontaminated graphite product.

该项目旨在开发一种有效且具有成本效益的方法来管理碳质核废物流，包括核石墨，因为它是现有和拟议的新一代核反应堆系统（例如高温气体反应堆{HTGRs}）的任何拟议退役策略中最关键的方面之一，这些系统使用石墨作为慢化剂、反射器或结构材料。我们最近开发了一种获得专利的熔盐净化方法，该方法将分离受污染石墨中的大部分放射性成分，从而减少需要地质处置的中级废物的体积。该方法可以进一步开发，以允许对剩余的净化后的完整石墨基质进行潜在的再利用，进一步减少废物流体积和临时存储需求。该项目旨在开发这种石墨再利用的新方法，并评估其处理各种碳质废物流的适用性，这些废物流被确定为核退役管理局（NDA）在分类和隔离以及最大限度地减少废物量方面感兴趣的领域，包括石墨的压实或重新利用/再利用。因此，工作重点是开发扩大这种去污方法的方法，对废物流进行全面评估，包括再利用去污石墨产品的可行性。