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

该项目旨在开发一种有效和具有成本效益的方法来管理含碳核废料，包括核石墨，因为这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)的任何拟议退役战略中最关键的方面之一，这些核反应堆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去污方法，该方法将分离受污染的石墨中的大多数放射性成分，减少需要地质处置的中级废物的数量。这种方法可以进一步开发，以允许潜在地重复使用剩余的去污染完整的石墨基质，进一步减少废流量和临时存储需求。该项目旨在开发这种石墨再利用的新方法，并评估其对处理各种含碳废气的适用性，这些废气被确定为核退役管理局(NDA)在分类和分离方面感兴趣的领域，并将废物量降至最低，包括石墨的压实或再利用/再利用。因此，工作的重点将是制定扩大这种去污方法的方法，对废流进行全面评估，包括重新使用去污的石墨产品的可行性。

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.