Please use this identifier to cite or link to this item: https://apo.ansto.gov.au/dspace/handle/10238/12979
Title: Modelling of reusable target materials for the production of fission produced 99Mo using MCNP6.2 and CINDER90
Authors: Raposio, R
Braoudakis, G
Rosenfeld, AB
Thorogood, GJ
Keywords: Molybdenum 99
Radioisotopes
Uranium
Radioactive wastes
Radiopharmaceuticals
Enriched uranium
Issue Date: Oct-2021
Publisher: Elsevier
Citation: Raposio, R., Braoudakis, G., Rosenfeld, A., & Thorogood, G. J. (2021). Modelling of reusable target materials for the production of fission produced 99Mo using MCNP6. 2 and CINDER90. Applied Radiation and Isotopes, 176, 109827. 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. © 2021 Elsevier Ltd.
URI: https://doi.org/10.1016/j.apradiso.2021.109827
https://apo.ansto.gov.au/dspace/handle/10238/12979
ISSN: 0969-8043
Appears in Collections:Journal Articles

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