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

这个项目的目的是制订一种有效和具有成本效益的办法来管理含碳核废料流，包括核石墨，因为它是任何拟议的现有和拟议的新一代核反应堆系统（例如使用石墨作为慢化剂、反射器或结构材料的高温气体反应堆）退役战略中最关键的方面之一。我们最近开发了一种专利熔盐净化方法，该方法将分离污染石墨中的大部分放射性成分，减少需要地质处理的中间水平废物的体积。这种方法可以进一步发展，以允许剩余的净化完好的石墨基体的潜在再利用，进一步减少废物流的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，并评估其对各种含碳废物流处理的适用性，这是核退役管理局（NDA）对分类和隔离以及减少废物量（包括石墨的压实或重新利用/再利用）感兴趣的领域。因此，工作重点将放在开发扩大这种净化方法的方法上，同时对废物流进行全面评估，包括重新使用净化石墨产品的可行性。

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.