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首页> 外文学位 >Inhalation dose assessment: Risk assessment of airborne particulates to workers in the Florida phosphate industry.
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Inhalation dose assessment: Risk assessment of airborne particulates to workers in the Florida phosphate industry.

机译：吸入剂量评估：对佛罗里达磷酸盐行业工人的空气中颗粒物的风险评估。

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摘要

Health risks to workers in the Florida phosphate industry due to inhalation of particulates containing radioactive materials were investigated. Site-specific particle database were established, and were integrated into a full dosimetry assessment. Particle mass concentration varies widely by plants and locations over 1 to 3 orders of magnitude. A majority of samplings indicate that particle mass is concentrated at large particle sizes. A unity shape factor was assigned for dose assessment after particle shape analysis. Mass density of the particles ranges from 1.6 to 1.7 g cm-3. Radioactivity concentrations of 238U, 226Ra, and 210Pb in products or particles range 1088--4151, 30--141, and 248--3204 Bq kg -1, respectively.; An application method of cascade impactor sampling data to dose assessment was presented. Effective dose scaling factors generated in this study reduce computational efforts for dose assessment.; Inhalation dose was calculated using site-specific particle size distribution data. Under the least conservative assumption of radionuclide-specific lung solubility, effective doses at granulator, storage, and shipping areas are 0.31 +/- 0.12, 0.27 +/- 0.07, and 0.22 +/- 0.02 mSv year -1, respectively. In contrast, under the most conservative assumption the effective doses are 2.24 +/- 2.53, 1.26 +/- 1.19, and 0.56 +/- 0.36 mSv year-1 at the same areas.; Solubility of uranium, thorium, and lead in particles were determined by an in-vitro solubility test. More than 94% of phosphate is dissolved in 1 day. However, 238U, 232Th, and 208Pb are not dissolved rapidly with the surrounding matrix. Retention of uranium and lead is similar to type M materials, and retention of thorium to type S materials as defined in the default clearance parameters of the ICRP 66 HRTM.; All measured data and dose calculation methods were integrated into a full internal dosimetry assessment. Site-specific effective doses range 0.24--0.68 mSv year-1 at granulator area, 0.21--0.49 mSv year-1 at storage area, and 0.21--0.27 mSv year-1 at shipping area. All results are smaller than dose limit of the general public. Compared with occupational dose limit, effective dose to workers in the Florida phosphate industry is extremely unlikely to approach or exceed the limit.
机译：调查了由于吸入含放射性物质的微粒而对佛罗里达磷酸盐行业工人的健康风险。建立了特定地点的颗粒数据库，并将其集成到完整的剂量学评估中。颗粒质量浓度随植物和位置的不同而变化很大，超过1至3个数量级。大多数采样表明颗粒质量集中在大颗粒尺寸上。颗粒形状分析后，分配一个统一的形状因子进行剂量评估。颗粒的质量密度为1.6至1.7g cm-3。产物或颗粒中的238U，226Ra和210Pb放射性浓度分别为1088--4151、30--141和248--3204 Bq kg -1。提出了级联冲击器采样数据在剂量评估中的应用方法。在这项研究中产生的有效剂量比例因子减少了剂量评估的计算工作。使用特定部位的粒度分布数据计算吸入剂量。在放射性核素特异性肺溶解度的最保守假设下，-1年制粒机，储存区和运输区的有效剂量分别为0.31 +/- 0.12、0.27 +/- 0.07和0.22 +/- 0.02 mSv。相反，在最保守的假设下，同一区域的有效剂量分别为2.24 +/- 2.53、1.26 +/- 1.19和0.56 +/- 0.36 mSv year-1。铀，or和铅在颗粒中的溶解度通过体外溶解度测试确定。 1天之内溶解了超过94％的磷酸盐。但是，238U，232Th和208Pb不能与周围的基质快速溶解。保留的铀和铅与M型材料相似，保留的to与S型材料相似，如ICRP 66 HRTM的默认清除参数所定义。所有的测量数据和剂量计算方法都集成到完整的内部剂量测定评估中。站点特定的有效剂量在制粒机区域范围为0.24--0.68 mSv year-1，在存储区域范围为0.21 --- 0.49 mSv year-1，在运输区域范围为0.21-0.27 mSv year-1。所有结果均小于公众的剂量极限。与职业剂量限值相比，佛罗里达磷酸盐行业工人的有效剂量极不可能接近或超过限值。

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  • 作者

    Kim, Kwang Pyo.;

  • 作者单位

    University of Florida.;

  • 授予单位 University of Florida.;
  • 学科 Engineering Nuclear.; Engineering Environmental.; Health Sciences Occupational Health and Safety.
  • 学位 Ph.D.
  • 年度 2005
  • 页码 225 p.
  • 总页数 225
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;环境污染及其防治;职业性疾病预防;
  • 关键词

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