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粒径对模拟胃肠道液中铀气溶胶溶解的影响。

Particle Size Dependent Dissolution of Uranium Aerosols in Simulated Gastrointestinal Fluids.

机构信息

Department of Medical Radiation Physics, and Department of Health, Medicine and Caring Sciences, Linköping University, Linköping, Sweden.

Department of Health, Medicine and Caring Sciences, Linköping University, Linköping, Sweden.

出版信息

Health Phys. 2023 Apr 1;124(4):285-300. doi: 10.1097/HP.0000000000001668. Epub 2023 Jan 20.

Abstract

Uranium aerosol exposure can be a health risk factor for workers in the nuclear fuel industry. Good knowledge about aerosol dissolution and absorption characteristics in the gastrointestinal tract is imperative for solid dose assessments and risk management. In this study, an in vitro dissolution model of the GI tract was used to experimentally study solubility of size-fractionated aerosols. The aerosols were collected from four major workshops in a nuclear fuel fabrication plant where uranium compounds such as uranium hexafluoride (UF 6 ), uranium dioxide (UO 2 ), ammonium uranyl carbonate, AUC [UO 2 CO 3 ·2(NH 4 ) 2 CO 3 ] and triuranium octoxide (U 3 O 8 ) are present. The alimentary tract transfer factor, f A , was estimated for the aerosols sampled in the study. The transfer factor was derived from the dissolution in the small intestine in combination with data on absorption of soluble uranium. Results from the conversion workshop indicated a f A in line with what is recommended (0.004) by the ICRP for inhalation exposure to Type M materials. Obtained transfer factors, f A , for the powder preparation and pelletizing workshops where UO 2 and U 3 O 8 are handled are lower for inhalation and much lower for ingestion than those recommended by the ICRP for Type M/S materials f A = 0.00029 and 0.00016 vs. 0.0006 and 0.002, respectively. The results for ingestion and inhalation f A indicate that ICRP's conservative recommendation of f A for inhalation exposure is applicable to both ingestion and inhalation of insoluble material in this study. The dissolution- and subsequent absorption-dependence on particle size showed correlation only for one of the workshops (pelletizing). The absence of correlation at the other workshops may be an effect of multiple chemical compounds with different size distribution and/or the reported presence of agglomerated particles at higher cut points having more impact on the dissolution than particle size. The impact on dose coefficients [committed effective dose (CED) per Bq] of using experimental f A vs. using default f A recommended by the ICRP for the uranium compounds of interest for inhalation exposure was not significant for any of the workshops. However, a significant impact on CED for ingestion exposure was observed for all workshops when comparing with CED estimated for insoluble material using ICRP default f A . This indicates that the use of experimentally derived site-specific f A can improve dose assessments. It is essential to acquire site-specific estimates of the dissolution and absorption of uranium aerosols as this provides more realistic and accurate dose- and risk-estimates of worker exposure. In this study, the results indicate that ICRP's recommendations for ingestion of insoluble material might overestimate absorption and that the lower f A found for inhalation could be more realistic for both inhalation and ingestion of insoluble material.

摘要

铀气溶胶暴露可能是核燃料行业工人的健康风险因素。对于固体剂量评估和风险管理,了解气溶胶在胃肠道中的溶解和吸收特性是至关重要的。在这项研究中,使用胃肠道的体外溶解模型来实验研究不同粒径气溶胶的溶解度。气溶胶是从核燃料制造厂的四个主要车间收集的,其中存在铀化合物,如六氟化铀(UF6)、二氧化铀(UO2)、碳酸铀酰铵、AUC[UO2CO3·2(NH4)2CO3]和八氧化三铀(U3O8)。研究中采样的气溶胶的肠道转移因子 fA 被估计。转移因子是从小肠溶解与可溶性铀吸收数据相结合得出的。来自转化车间的结果表明,fA 与 ICRP 为吸入暴露于 M 型材料推荐的一致(0.004)。在粉末制备和制粒车间处理 UO2 和 U3O8 的情况下,获得的 fA 对于吸入和摄入的转移因子都低于 ICRP 为 M/S 材料推荐的 fA=0.00029 和 0.00016 ,分别为 0.0006 和 0.002。对于摄入和吸入 fA 的结果表明,ICRP 对吸入暴露的保守推荐的 fA 适用于本研究中不可溶物质的摄入和吸入。溶解和随后的吸收对粒径的依赖性仅与一个车间(制粒)有关。在其他车间没有相关性可能是由于不同粒径分布的多种化合物的影响,或者报道的高截断点处存在团聚颗粒对溶解的影响大于粒径。对于任何车间,使用实验性 fA 与使用 ICRP 为吸入暴露的感兴趣铀化合物推荐的默认 fA 相比,对剂量系数[每 Bq 承诺有效剂量(CED)]的影响都不显著。然而,当将使用 ICRP 默认 fA 对不可溶物质进行估算的 CED 与所有车间的摄入暴露的 CED 进行比较时,对于所有车间的 CED 都观察到了显著的影响。这表明使用实验性获得的特定部位的 fA 可以改善剂量评估。获取铀气溶胶溶解和吸收的特定部位的估计值至关重要,因为这可以提供更现实和准确的工人暴露剂量和风险估计值。在这项研究中,结果表明,ICRP 对不可溶物质摄入的建议可能高估了吸收,并且对于吸入和不可溶物质摄入,发现的较低 fA 可能更现实。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/3c1e/9940842/c086f6530794/hpj-124-285-g001.jpg

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