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用于估算马亚克生产联合企业核电站工人钚肺部清除情况以进行暴露评估的模型开发。

The development of the plutonium lung clearance model for exposure estimation of the Mayak production association, nuclear plant workers.

作者信息

Khokhryakov Valentin F, Suslova Klara G, Vostrotin Vadim V, Romanov Sergey A, Menshikh Zoya S, Kudryavtseva Tamara I, Filipy Ronald E, Miller Scott C, Krahenbuhl Melinda P

机构信息

Branch No. 1 Federal Research Center Biophysics Institute, Ozyorsk Chelyabinsk Region, Russia.

出版信息

Health Phys. 2002 Apr;82(4):425-31. doi: 10.1097/00004032-200204000-00001.

Abstract

The purpose of this study was to develop a biokinetic model that uses urinary plutonium excretion rate data to estimate the plutonium accumulation in the human respiratory tract after occupational exposure. The model is based on autopsy and urinalysis data, specifically the plutonium distribution between the respiratory tract and the remainder of the body, taken from 543 former workers of a radiochemical facility at the Mayak Production Association (MPA) plant. The metabolism of plutonium was represented with a compartmental model, which considers individual exposure histories and the inherent solubility properties of industrial plutonium aerosols. The transport properties of plutonium-containing aerosols were estimated by experimentally defining their in vitro solubility. The in vitro solubilities were found by dialysis in a Ringer's solution. Analysis of the autopsy data indicated that a considerable fraction of the inhaled plutonium is systemically redistributed rapidly after inhalation. After the initial dynamic period, a three-compartment model describes the retention in the respiratory tract. One compartment describes the nuclide retained in the lungs, the second compartment describes a plutonium lung concentration that exponentially decreases with time, and the third compartment describes the concentration in the pulmonary lymph nodes. The model parameters were estimated by minimizing sum squared of the error between the tissue and bioassay data and the model results. The parameters reflect the inverse relationship between plutonium retention in lungs and the experimentally derived aerosol transportability. The model was validated by comparing the autopsy results with in vivo data for 347 cases. The validation indicates that the model parameters are unbiased. This model is being used to estimate individual levels of nuclide accumulation and to compute radiation doses based upon the urinary excretion rates.

摘要

本研究的目的是建立一个生物动力学模型,该模型利用尿钚排泄率数据来估算职业暴露后人体呼吸道中钚的蓄积量。该模型基于尸检和尿液分析数据,特别是从玛雅克生产协会(MPA)工厂的一家放射化学设施的543名前工人身上获取的呼吸道与身体其他部位之间的钚分布数据。钚的代谢用一个房室模型来表示,该模型考虑了个体暴露史和工业钚气溶胶的固有溶解性。通过实验确定含钚气溶胶的体外溶解性来估算其传输特性。体外溶解性通过在林格氏溶液中进行透析来测定。对尸检数据的分析表明,吸入的钚中有相当一部分在吸入后迅速进行全身再分布。在初始动态期之后,一个三室模型描述了呼吸道中的滞留情况。一个房室描述了滞留在肺部的核素,第二个房室描述了随时间呈指数下降的钚肺浓度,第三个房室描述了肺淋巴结中的浓度。通过最小化组织和生物测定数据与模型结果之间误差的平方和来估计模型参数。这些参数反映了钚在肺部的滞留与实验得出的气溶胶可传输性之间的反比关系。通过将347例尸检结果与体内数据进行比较对该模型进行了验证。验证表明模型参数无偏差。该模型正用于根据尿排泄率估算个体核素蓄积水平并计算辐射剂量。

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