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首页> 外文期刊>Health Physics: Official Journal of the Health Physics Society >Solubility characterization of airborne uranium from a uranium recycling plant.
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Solubility characterization of airborne uranium from a uranium recycling plant.

机译:来自铀回收厂的机载铀的溶解度表征。

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Solubility profiles of uranium dusts in a uranium recycling plant were determined by performing in vitro solubility tests on breathing zone air samples conducted in all process areas of the processing plant. The recycling plant produces high density shields, closed end tubes that are punched and formed from uranium sheet metal, and high-fired uranium oxide, which is used as a catalyst. The recycled uranium is cut and melted in a vacuum furnace, and part of the molten uranium is poured into molds for further processing. Air samples were taken in process areas under normal working conditions. The dissolution rate of the uranium in a simulant solution of extracellular airway lining fluid (Gamble's solution) was then determined over the next 28 d. Airborne uranium in the oxide section of the plant was found to be highly insoluble with 99% of the uranium having a dissolution half time in excess of 100 d. The solubility of the airborne uranium in other areas of the facility was only slightly more soluble with over 90% of the airborne uranium having dissolution half times in excess of 90 d.
机译:通过对在加工厂的所有过程区域中进行的呼吸区空气样品进行体外溶解度测试,可以确定铀回收工厂中铀粉尘的溶解度分布。回收工厂生产高密度防护罩,由铀金属板材冲压成型的封闭端管以及用作催化剂的高燃烧铀氧化物。将回收的铀切割并在真空炉中熔化,然后将部分熔融的铀倒入模具中进行进一步处理。在正常工作条件下,在过程区域中采集了空气样本。然后在接下来的28 d中确定铀在细胞外气道内衬液模拟溶液(Gamble's溶液)中的溶解速率。发现工厂氧化层中的空气中铀是高度不溶的,其中99%的铀的溶解半衰期超过100 d。机载铀在设施其他区域的溶解度仅稍高一些,超过90%的机载铀的溶解度超过90 d的一半。

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