In-situ tritium contamination and decontamination of fusion-relevant materials

Nuclear fusion could offer a solution to the growing global demand for clean, sustainable and abundant energy. The deuterium-tritium fusion reaction offers a high energy yield and feasibility at achievable temperatures. However, the scarcity and radioactive nature of tritium pose significant challenges for its handling in fusion reactors. Tritium adsorption onto surfaces leads to challenges in licensing, process control and maintenance. Ozone is a known decontaminant and may provide a viable solution for the decontamination of these tritiated surfaces. Due to its strong oxidising nature, ozone reacts with the adsorbed tritium, which can then be evacuated. This study aims to investigate tritium accumulation and decontamination on the fusion-relevant materials: beryllium, EUROFER97 and tungsten. These are selected for their critical roles in reactor components and tritium-processing systems. The findings will provide insights into the behaviour of tritium in these materials and assess the potential of ozone-based decontamination techniques compared to established methods. This contributes to the development of effective strategies for tritium handling, decontamination and inventory management in future fusion reactors.