Modelling of reusable target materials for the production of fission produced ⁹⁹Mo using MCNP6.2 and CINDER90

Current fission-based methods of ⁹⁹Mo production require single use uranium targets which leads to spent uranium waste. This waste could be reduced if a target is developed that does not require dissolution so that it can be reused for multiple production runs. MCNP6.2 was used to model reusable targets of 20% and 1% enrichment for activity produced, target efficiency and burnup. The 1% enriched target was found to be much more efficient but had a lower activity produced compared to the 20% enriched target. The ideal target design for ⁹⁹Mo production that optimises efficiency and reusability and reduces the self-shielding effect of UO₂ was found to be a target that is made from 1% enriched UO₂ with density as high as allowable for sufficient yields, efficient ⁹⁹Mo extraction and having an irradiation time of 5 days, with the target able to be re-irradiated and re-processed 2-4 times.