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

点击翻译按钮获取中文摘要

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.