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Modelling of reusable target materials for the production of fission produced 99Mo using MCNP6.2 and CINDER90
Applied Radiation and Isotopes ( IF 1.6 ) Pub Date : 2021-06-12 , DOI: 10.1016/j.apradiso.2021.109827
Robert Raposio 1 , George Braoudakis 2 , Anatoly Rosenfeld 1 , Gordon J Thorogood 2
Affiliation  

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.



中文翻译:

使用 MCNP6.2 和 CINDER90 对用于生产裂变产生的 99Mo 的可重复使用目标材料进行建模

当前基于裂变的99 Mo 生产方法需要一次性使用的铀靶,这会导致废铀废物。如果开发的靶材不需要溶解,从而可以重复用于多次生产运行,则可以减少这种浪费。MCNP6.2 用于模拟 20% 和 1% 富集的可重用目标,用于产生的活动、目标效率和燃耗。发现与 20% 富集的目标相比,1% 富集的目标效率更高,但产生的活性较低。发现优化效率和可重复使用性并降低 UO 2自屏蔽效应的99 Mo 生产的理想靶材设计是由 1% 富集的 UO 2制成的靶材密度达到足够高的产量,高效提取99 Mo,辐照时间为 5 天,靶材可以再辐照和再加工 2-4 次。

更新日期:2021-06-17
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