Department of Medical Radiation Physics, and Department of Health, Medicine and Caring Sciences, Linköping University, Linköping, Sweden.
European Spallation Source ERIC, P.O Box 176, SE-221 00 Lund, Sweden.
Health Phys. 2022 Jul 1;123(1):11-27. doi: 10.1097/HP.0000000000001564. Epub 2022 May 6.
Inhalation exposure to uranium aerosols can be a concern in nuclear fuel fabrication. The ICRP provides default absorption parameters for various uranium compounds but also recommends determination of material-specific absorption parameters to improve dose calculations for individuals exposed to airborne radioactivity. Aerosol particle size influences internal dosimetry calculations in two potentially significant ways: the efficiency of particle deposition in the various regions of the respiratory tract is dependent on aerodynamic particle size, and the dissolution rate of deposited materials can vary according to particle size, shape, and porosity because smaller particles tend to have higher surface-to-volume ratios than larger particles. However, the ICRP model assumes that deposited particles of a given material dissolve at the same rate regardless of size and that uptake to blood of dissolved material normally occurs instantaneously in all parts of the lung (except the anterior portion of the nasal region, where zero absorption is assumed). In the present work, the effect of particle size on dissolution in simulated lung fluid was studied for uranium aerosols collected at the plant, and its influence on internal dosimetry calculations was evaluated. Size fractionated uranium aerosols were sampled at a nuclear fuel fabrication plant using portable cascade impactors. Absorption parameters, describing dissolution of material according to the ICRP Human Respiratory Tract Model, were determined in vitro for different size fractions using simulated lung fluid. Samples were collected at 16 time-points over a 100-d period. Uranium content of samples was determined using inductively coupled plasma mass spectrometry and alpha spectrometry. In addition, supplementary experiments to study the effect of pH drift and uranium adsorption on filter holders were conducted as they could potentially influence the derived absorption parameters. The undissolved fraction over time was observed to vary with impaction stage cut-point at the four main workshops at the plant. A larger fraction of the particle activity tended to dissolve for small cut-points, but exceptions were noted. Absorption parameters (rapid fraction, rapid rate, and slow rate), derived from the undissolved fraction over time, were generally in fair agreement with the ICRP default recommendations for uranium compounds. Differences in absorption parameters were noted across the four main workshops at the plant (i.e., where the aerosol characteristics are expected to vary). The pelletizing workshop was associated with the most insoluble material and the conversion workshop with the most soluble material. The correlation between derived lung absorption parameters and aerodynamic particle size (impactor stage cut-point) was weak. For example, the mean absorption parameters derived from impaction stages with low (taken to be <5 μm) and large (≥5 μm) cut-points did not differ significantly. Drift of pH and adsorption on filter holders appeared to be of secondary importance, but it was found that particle leakage can occur. Undissolved fractions and to some degree derived lung absorption parameters were observed to vary depending on the aerodynamic size fraction studied, suggesting that size fractionation (e.g., using cascade impactors) is appropriate prior to conducting in vitro dissolution rate experiments. The 0.01-0.02 μm and 1-2 μm size ranges are of particular interest as they correspond to alveolar deposition maxima in the Human Respiratory Tract Model (HRTM). In the present work, however, the dependency on aerodynamic size appeared to be of minor importance, but it cannot be ruled out that particle bounce obscured the results for late impaction stages. In addition, it was noted that the time over which simulated lung fluid samples are collected (100 d in our case) influences the curve-fitting procedure used to determine the lung absorption parameters, in particular the slow rate that increased if fewer samples were considered.
吸入铀气溶胶可能是核燃料制造过程中的一个关注点。ICRP 为各种铀化合物提供了默认的吸收参数,但也建议确定特定于材料的吸收参数,以改进对暴露于空气中放射性的个体的剂量计算。气溶胶颗粒大小以两种潜在的显著方式影响内部剂量计算:颗粒在呼吸道各个区域的沉积效率取决于空气动力学颗粒大小,而沉积材料的溶解速率可能根据颗粒大小、形状和孔隙率而变化,因为较小的颗粒比较大的颗粒往往具有更高的表面积与体积比。然而,ICRP 模型假设给定材料的沉积颗粒以相同的速率溶解,而不考虑大小,并且溶解物质向血液中的摄取通常在肺部的所有部位(除了假定为零吸收的鼻腔前部)中瞬间发生。在本工作中,研究了在工厂收集的铀气溶胶在模拟肺液中的溶解对颗粒大小的影响,并评估了其对内部剂量计算的影响。使用便携式级联撞击器在核燃料制造工厂对铀气溶胶进行了粒径分级采样。使用模拟肺液在体外为不同粒径的物质确定了描述根据 ICRP 人体呼吸道模型的溶解的吸收参数。在 100 天的时间内,在 16 个时间点收集了样品。使用电感耦合等离子体质谱法和α谱法测定样品中的铀含量。此外,还进行了补充实验以研究 pH 漂移和铀吸附对滤器支架的影响,因为它们可能会影响衍生的吸收参数。随着时间的推移,观察到未溶解部分随工厂四个主要车间的撞击阶段截止点而变化。较小的截止点往往会溶解更大比例的颗粒活性,但也有例外。从随时间推移的未溶解部分得出的吸收参数(快速部分、快速率和慢速率)通常与 ICRP 对铀化合物的默认建议相符。在工厂的四个主要车间(即气溶胶特性预计会有所不同的地方)之间注意到吸收参数的差异。制粒车间与最不溶性材料有关,而转化车间与最可溶性材料有关。从衍生的肺吸收参数与空气动力学颗粒大小(撞击阶段截止点)之间的相关性较弱。例如,从低(<5 μm)和大(≥5 μm)截止点的撞击阶段得出的平均吸收参数没有显著差异。pH 值漂移和对滤器支架的吸附似乎是次要的,但发现可能会发生颗粒泄漏。未溶解部分和在某种程度上衍生的肺吸收参数被观察到取决于所研究的空气动力学粒径,这表明在进行体外溶解速率实验之前,进行粒径分级(例如使用级联撞击器)是合适的。0.01-0.02 μm 和 1-2 μm 粒径范围特别有趣,因为它们对应于人体呼吸道模型(HRTM)中的肺泡沉积最大值。然而,在本工作中,空气动力学尺寸的依赖性似乎不太重要,但不能排除颗粒反弹掩盖了后期撞击阶段的结果。此外,需要注意的是,模拟肺液样品的采集时间(在我们的情况下为 100 天)会影响用于确定肺吸收参数的曲线拟合过程,特别是如果考虑较少的样本,慢速率会增加。