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

Robert Raposio; George Braoudakis; Anatoly Rosenfeld; Gordon J Thorogood

doi:10.1016/j.apradiso.2021.109827

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

Appl Radiat Isot. 2021 Oct:176:109827. doi: 10.1016/j.apradiso.2021.109827. Epub 2021 Jun 12.

Authors

Robert Raposio¹, George Braoudakis², Anatoly Rosenfeld³, Gordon J Thorogood²

Affiliations

¹ University of Wollongong, Australia. Electronic address: rra@ansto.gov.au.
² Australian Nuclear Science and Technology Organisation, Australia.
³ University of Wollongong, Australia.

PMID: 34144410
DOI: 10.1016/j.apradiso.2021.109827

Abstract

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.

Keywords: (99)Mo production; MCNPX; Uranium targets; Waste minimisation.