共查询到18条相似文献,搜索用时 218 毫秒
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依据更丰富的受照人员实测数据,以国际放射防护委员会(ICRP)141号报告呼吸道模型及系统模型为代表的新模型及剂量转换系数相比旧模型及剂量转换系数具有更高可信度。对于目前超铀核素吸入后的基于间接测量的内照射评价来说,新、旧模型带来的计算结果的异同很重要。本文基于ICRP 141号报告为代表的新生物动力学模型建立超铀核素的滞留、排泄份额计算程序,并分别对工作参考人吸入S、M、F类241Am气溶胶(AMAD 5 μm)后的尿、粪排泄份额进行新、旧模型计算值对比,发现了新、旧模型计算值的显著差异,且基于尿、粪样中241Am估算有效剂量上,新、旧模型计算结果的差异也显著。基于尿粪的间接测量的内照射评价标准后期可视情况根据新模型计算值进行修订。 相似文献
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正用于放射性核素内照射评价的剂量系数是辐射防护量,决定食入或吸入放射性核素后每单位摄入量所致的器官当量剂量或有效剂量。在ICRP关于放射性核素职业性摄入(OIR)系列出版物中,提出了关于进入体内的核素放射性核素分布的新动力学模型,以确定放射性核素在沉积器管(源区)内的时间积分浓度。 相似文献
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ICRP66、67号出版物中对内照射剂量估算中使用的呼吸道模型和Pu在人体内代谢模式进行了较大的修改。本文应用ICRP66、67号出版筇的推荐的Pu在人体内的代谢模型及参数及新呼吸道模型,估算了一例^239Pu内污染者的摄入量和待积有效剂量。 相似文献
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不同的生物动力学模型给出的氚的摄入量滞留函数和剂量转换系数存在明显的差别。Crawford-Brown模型在氚化学形态转化描述和年龄段剂量转换系数分析上具有独特优势,本文在比较不同模型研究进展的基础上,重点对Crawford-Brown模型进行计算,给出不同年龄段的氚滞留函数和剂量转换系数,并同其他模型计算结果进行了详细的比较。结果显示,除了成人摄入氚水情况,Crawford-Brown模型计算给出的不同年龄段人群摄入氚水和有机氚的剂量转换系数都会比ICRP模型的高。随着年龄的减小,氚水和有机氚的相互转换愈发明显,剂量转换系数上的差别愈发明显。成人氚水摄入量滞留函数的比较表明,几种模型在100 d内的滞留函数曲线几乎完全相同,只在长期滞留项上存在显著差别。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(8):665-668
A method is proposed to estimate parameters for dose calculation from inhaled activity distribution in the human body. Inhalation of 60Co aerosols is simulated by the metabolic model proposed in ICRP Publication 30. The ranges of parameters for dose calculation are as follows: particle size 1 to 20 μm; inhalation class Y; time after inhalation 1 to 90 d. The ratio of radionuclide retentions in the lower to upper bodies, divided by the diaphragm, is used as the index of activity distribution in the body. The results of computer simulations show that the retained activity ratio is valid to estimate intervals of possible values of particle size and time after inhalation. 相似文献
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I. B. Keirim-Markus 《Atomic Energy》2002,93(4):836-844
Epidemiological studies of the consequences of radiation exposure of humans already prove that at low dose rates 85% of radiation-induced cancer arises only above a threshold dose from 0.3 to 30 Sv, and sometimes radiation hormesis occurs. In this question, the ICRP and the RNCRP rely on unreliable information and an incorrect linear zero-threshold dose–effect relation model. Two new principles of radiation safety are proposed and a model for normalizing radiation exposure on the basis of the new facts is also proposed. The model retains the adopted maximum lifetime individual risk of death due to radiation-induced cancer, but the dose in organs determines this risk. For uniform whole body radiation exposure, the dose creating the indicated limit can be taken as the equivalent dose. It will equal 150 mSv/yr. According to the model, during the initial years of radiation exposure there is no carcinogenic risk at all. The need for normalizing the content of radionuclides in the human body and introducing other changes in the norms is substantiated. 相似文献
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氡子体比是指其短寿命子体218 Po、214 Pb、214 Bi的活度浓度的比值,是氡子体剂量评价中的重要参数,但环境中氡子体比的数据非常有限。为了解和把握城市典型环境中氡子体比的现状,并分析其对剂量转换系数的影响,本文利用便携式α谱仪,现场测量了城市典型室内外环境的氡子体比,并通过分析室内外环境氡子体比数据的特点,讨论了环境氡子体比对剂量转换系数的影响。测量结果显示,城市典型室内环境中氡子体比的平均值为1∶0.59∶0.58,典型室外环境中氡子体比的平均值为1∶0.50∶0.67。因各子体的剂量系数与它们的α潜能呈正比,所以氡子体比对剂量转换系数的影响很小。 相似文献
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点核积分方法是辐射剂量计算的基本方法之一,广泛应用于辐射防护领域。传统的点核剂量计算中采用文本方式描述计算模型,存在难以描述复杂几何、易出错且耗时的问题。针对该问题,本文基于FDS团队自主研发的超级蒙卡核模拟软件系统SuperMC,进行了基于CAD的点核剂量计算方法研究与程序开发,可基于实际问题的CAD模型直接进行支持多重源的光子点核剂量计算,提高了程序对复杂三维几何问题的处理能力,并包含较为完备的核数据库。使用ANSI/ANS6.6.1、ESIS和VisiPlan的基准例题对程序进行了测试验证,测试结果与VisiPlan4.0对比吻合良好。同时将该方法初步应用于ITER热室屏蔽的设计中,说明了本方法及程序处理复杂场景问题的能力。 相似文献
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Valentin J 《Annals of the ICRP》2002,32(1-2):13-306
The ICRP Publication 66 Human Respiratory Tract Model for Radiological Protection (HRTM) has been applied to calculate dose coefficients (doses per unit intake) and bioassay functions in ICRP Publications 68, 71, 72 and 78. For these purposes, ICRP assigned numerical values to a range of model parameters, such as the size of the inhaled particles and the breathing rate of the subjects. These are known as 'default' or 'reference' values, and were chosen to be typical, representative values. In any particular situation the actual values of many parameters can be considerably different from the reference values. Usually, doses from intakes of radionuclides are low compared with the relevant limit or constraint, and the resulting difference is unimportant. There are, however, circumstances where more reliable assessments of intake and dose are desirable. This Guidance Document therefore gives advice on applying specific information within the framework of the HRTM for assessing occupational and environmental exposures and for interpreting bioassay data. Chapters on each aspect of the model (morphometry, physiology, deposition, clearance, gases and vapours, dosimetry) provide: A summary of how the HRTM treats that topic;Information on the reference values of relevant parameters;Guidance on choosing between default values;Information on how doses and bioassay quantities (lung retention, urine, and faecal excretion) vary with the values of selected parameters, giving guidance on the importance of obtaining specific information;Simple examples of the use of specific information relating to the topic.Annexes give additional information for those directly involved in applying the HRTM to specific situations, including guidance on obtaining parameter values. A brief overview is given of the deposition, characterisation, and sampling of aerosols, with references to further information, as there are relevant text books already available. Issues specific to radioactive aerosols, such as low particle number concentrations for high specific activity materials are, however, addressed. Guidance on obtaining information about absorption of inhaled radionuclides into blood is given in greater detail, because this is a topic on which ICRP has traditionally given guidance, and because a compilation of such information is not readily available elsewhere. Several detailed examples are also provided. One involves assessment of an individual's intake and committed dose from comprehensive bioassay monitoring data. The others deal with the derivation of HRTM absorption parameter values from experimental data, and their application, with additional information on e.g. size distribution, to calculate dose coefficients and interpret bioassay data. 相似文献
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在评价公众成员摄入放射性核素的辐射危害时,需估算每单位摄入量所致的剂量。摄入放射性素后器官或民受到的剂量是受到的剂量是通过生物学模型和剂量学模型来确定的,因此剂量也必须根据模型来确定。文中初步探讨了国际放射防护委员会给出的剂量系数的可靠性问题。文中首先说明了估算剂量系数的概念和方法,然后分析了剂量系数估算中,采用胃肠道模型,呼吸道模型,系统生物动力学模型和剂量学模型所遇到的不确定度的各种主要来源。 相似文献