Skip to main content
placeholder image

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

Journal Article


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.

Publication Date


  • 2021

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. doi:10.1016/j.apradiso.2021.109827

Scopus Eid


  • 2-s2.0-85107968133

Volume


  • 176

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.

Publication Date


  • 2021

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. doi:10.1016/j.apradiso.2021.109827

Scopus Eid


  • 2-s2.0-85107968133

Volume


  • 176