Effective dose coefficients for intakes of uranium radionuclides via contaminated wounds have been calculated for reference adults following the procedures in the ICRP 103 series. The number of transformations in each source region for all members of the radioactive series from time of intake to 50 y post intake are calculated by coupling the NCRP 156 wound model to the ICRP 137 systemic models and ICRP 100 human alimentary tract model. Together with the ICRP 107 nuclear decay data for dosimetric calculations, the ICRP 133 specific absorbed fractions are implemented to calculate the radiation-weighted S coefficient deposited in each target organ or tissue from each transformation in each source region. Effective dose coefficients for different categories of intake materials via contaminated wounds are calculated for the three major uranium isotopes-U, U, and U. Originating from the combined effects of the new absorbed fractions, biokinetic and dosimetric models, the new coefficients are generally reduced by a percentage of 23-28% as compared to the old ones. The new dose coefficients benefit the assessment of internal exposures for intakes of uranium via contaminated wounds in actual applications.

中文翻译：

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参考成人通过污染伤口摄入铀的有效剂量系数。

按照 ICRP 103 系列中的程序，为参考成人计算了通过受污染伤口摄入铀放射性核素的有效剂量系数。通过将 NCRP 156 伤口模型与 ICRP 137 系统模型和 ICRP 100 人类消化道模型耦合，计算放射性系列所有成员从摄入时间到摄入后 50 年的每个源区域的转化数量。与用于剂量计算的 ICRP 107 核衰变数据一起，实施 ICRP 133 特定吸收分数来计算每个源区域中每次变换沉积在每个目标器官或组织中的辐射加权 S 系数。针对三种主要铀同位素U、U和U，计算了通过受污染伤口不同类别摄入材料的有效剂量系数。由于新吸收分数、生物动力学和剂量模型的综合影响，新系数普遍减小与旧的相比，百分比提高了23-28%。新的剂量系数有利于评估实际应用中通过受污染伤口摄入铀的内照射。