粪样中241Am测量方法的探索

目的 对粪样中超铀核素²⁴¹Am的分析测量方法进行研究,初步建立粪样中²⁴¹Am的分析方法,为工作人员内照射监测提供技术支持。方法 利用自行研制的粪样取样器和碳化灰化炉对粪样采集处理;采用DGA树脂对粪样中²⁴¹Am进行分离纯化的方法研究,用²⁴³Am为示踪剂并采用正交法进行条件优化实验。结果 初步确定以6 Mol/LHNO₃为上柱酸度、0.6 mL/min上柱速度和解析体积为12 mL的最佳分离纯化的条件;同时基于ICP-MS对粪样进行质谱测量分析,确定了基于ICP-MS的²⁴¹Am的检出限为9.79×10^-4 Bq,测量结果理想,具有可行性。结论 本文建立的方法在一定程度上弥补了对粪样中²⁴¹Am测量方法研究的空缺,对内照射监测和分析人员保护有实际意义。     

电子计算器编程运算在估算放射性核素内照射累积剂量中的应用

由于辐射防护实践需要,国际辐射防护委员会(ICRP)30号出版物中给出了一整套有关内照射剂量学参数,其中包括放射性核素单位摄入待积有效剂量当量和待积器官(组织)剂量当量转换因子。这些转换因子都是以待积50年为基础提供的。只要放射性活度摄入量一旦被肯定,则50年内产生的累积器官(组织)剂量当量和累积有效剂量当量就能估算出来。无疑这对辐射內     

甘肃省3家医院核医学科放射工作人员内照射水平分析

目的 对甘肃省3家甲级医院的20名从事核医学工作的医务人员开展甲状腺中¹³¹I内照射监测和剂量估算。方法 使用InSpector 1000型便携式γ谱仪进行体外直接测量法。将谱仪进行能量刻度和效率刻度后，对每位工作人员的甲状腺和大腿部位分别进行一次测量，测量时间均为120 s。大腿部测得结果作为体内本底，计算甲状腺¹³¹I活度，利用甲状腺¹³¹I摄入量，计算甲状腺待积器官剂量并推算年待积有效剂量。结果 3家医院20名核医学工作人员其中8人甲状腺中检出¹³¹I，占总人数的40%，甲状腺中¹³¹I活度范围为：30.29～1271.68 Bq，平均活度为395.39 Bq；甲状腺待积器官剂量范围是0.33～14.00 μSv，平均剂量为4.36 μSv；年待积有效剂量范围是0.02～0.73 mSv，平均剂量为0.23 mSv。结论 调查结果显示，所有人员年待积有效剂量均未超过必须进行内照射监测的1 mSv限值，但也较为接近，可以适当调整监测周期。考虑到每个周期用药量及治疗病人数量的变化，还需要密切关注。     

基于ICRP生物动力学模型的镅急性吸入后在主要源器官中滞留份额计算

目的 为了避免超铀核素镅大量吸入造成对关键靶器官的伤害,并为事故后促排或其他辐射防护措施提供依据。方法 本研究依据IAEA通用安全导则No.GSG-2的内照射事故应急准备与响应通用准则、ICRP当前最新的生物动力学模型及参数,以工作人员急性吸入²⁴¹Am[粒径AMAD 5μm(σ=2.5)]为例建立计算程序,确定关键靶器官为肺部AI区和红骨髓,并确定造成关键靶器官短期吸收剂量的主要源器官为肺部AI区、血液、小梁骨骨表。结果 计算出²⁴¹Am吸入后主要源器官中滞留份额随时间的变化。结论 镅吸收入血后从血液中快速转移,不同吸收类别镅在血液中早期滞留份额变化趋势相似,S、M、F类镅在血液中滞留份额峰值出现在0.03 d左右,到约1.7 d时衰减到峰值的一半;镅吸入后在肺部AI区、小梁骨中的早期滞留份额随时间的变化趋势有所不同：S、M类镅在肺部AI区滞留份额随时间变化较小,F类镅从肺部快速被吸收入血;小梁骨中镅,S类在前7 d快速增加,M类主要在前2周逐渐增加,F类在前2 d较快速度增加。     

海阳核电站运行前周边地区食品中放射性水平及所致居民剂量

目的 对海阳核电站运行前周边地区食品中放射性核素进行分析,获取该地区放射性核素基线值,为评估核电站对人群的影响提供依据。方法 采集核电站周围50 km范围内居民日常食用的22种食品样品,进行预处理、测量,采用效率曲线法计算样品中所含放射性核素的活度浓度(Bq/kg),并估算当地居民由膳食摄入所致的待积有效剂量。结果 食品样品中检出的放射性核素为天然核素⁴⁰K、²³⁸U、²³²Th、²²⁶Ra以及人工核素¹³⁷Cs、⁶⁰Co,检出人工核素刚达到探测下限,其余人工核素¹³¹I、¹³⁴Cs、⁵⁸Co未检出;⁴⁰K、²³⁸U、²³²Th、²²⁶Ra、¹³⁷Cs的活度浓度平均值分别为12.858、0.550、0.146、0.077、0.016 Bq/kg,范围分别为0.0266~2.2736,0.0013~1.3599,0.0127~0.2568,0.0043~0.0555,0.0065~0.0065,2.433~30.4572 Bq/kg;放射性核素平均活度浓度由高到低依次为⁴⁰K > ²³⁸U > ²³²Th > ²²⁶Ra > ¹³⁷Cs > ⁶⁰Co,各种核素所致年待积有效剂量为39.21 μSv/a,其中人工核素为0.03 μSv/a。结论 所检测海阳核电站周边地区食品中人工核素除微量¹³⁷Cs、⁶⁰Co外,未见其他人工核素;食品中各种放射性核素活度浓度均在国家标准限值以内,对周围居民造成的剂量负担较小。     

我国五省核医学工作场所放射性核素浓度分析

目的 通过对不同地区5个省的部分临床核医学的调查,获取临床核医学工作场所主要放射性核素的空气中的活度浓度水平,并分析了临床核医学中相关人员的剂量水平,为建立适合我国国情的临床核医学防护规范提供依据。方法 选择5个省份的部分开展临床核医学的医院,对相关的场所进行空气采样,采用无源效率刻度方法进行γ能谱分析,计算得到各场所关注核素的空气中的活度浓度分布水平,估算相关场所中工作人员因放射性核素操作所致的年待积有效剂量。结果 对5个省的9家开展临床核医学的医疗机构核医学相关工作场所进行了采样测量,开展¹³¹I治疗的医院工作人员年待积有效剂量最大值为1.67×10⁻¹ mSv;开展⁹⁹Tc^m诊断的医院工作人员年待积有效剂量最大值为2.80×10⁻³ mSv;结论 不同的医院和场所中核素浓度水平差异较大。正常工作条件下,5个省份的9家医院核医学工作场所的工作人员年待积有效剂量均比国家标准对个人剂量的限值要求低很多。     

田湾核电站周围公众因铀钍系放射性核素摄入所致内照射剂量

目的 分析田湾核电站运行前30km范围内公众膳食结构,估算内照射剂量,为评估核电站辐射对人群的影响提供科学依据。方法 根据UNSCEAR 2000报告书中方法,统计食品消费量,分类计算食品中铀钍系放射性核素浓度,依据剂量转换系数分析内照射剂量。结果 与世界食品平均消费量比较,田湾核电站周围公众膳食特点为谷物、叶类制品和鱼制品年消费较多;铀钍系放射性核素致核电站周围公众年内照射待积有效剂量儿童为691μSv·a^-1,成人为327μSv·a^-1;成年人中渔民待积有效剂量536μSv·a^-1。结论 ²¹⁰Po、²¹⁰Pb和²²⁸Ra是经膳食影响田湾核电站周围公众内照射剂量的主要核素;渔民由于居住距离及膳食结构方面特点,应进一步关注其内照射剂量估算与评价;居民膳食结构特点和我国食品中部分核素的活度浓度较大是公众年待积有效剂量高的原因;需要定期调查掌握饮食状况和食谱变化。     

广东省食品和水中铀含量及卫生学评价

广西自60年代起开始应用放射性同位素于水文、地质物探,80、90年代陆续用于煤田地质勘探及石油天然气探测。全区计有测井源、仪表刻度源约150枚,核素为⁶⁰Co、²²⁶Ra、¹³⁷Cs、²¹⁰Po、¹⁰⁷Ru、²³²Th、²²⁶Ra-Be、²⁴¹Am、²⁴¹Am-Be等,活度范围3.7×10⁶~7.4×10¹¹Bq(0.1mCi~20Ci)。     

便携式γ谱仪在放射工作人员甲状腺131I监测中的应用

目的 将InSpector 1000便携式γ谱仪及其相应配套软件应用于放射工作人员甲状腺¹³¹I活度的监测中,监测核医学科放射工作人员内照射剂量。方法 对谱仪进行刻度并参加了美国劳伦斯·利弗莫尔国家实验室发起的2018年甲状腺放射性碘比对计划,确保测量的准确性;利用该谱仪分别对北京市与济南市的2家三甲医院核医学科放射工作人员进行测量以验证方法的可行性。结果 该InSpector 1000便携式γ谱仪参加国际比对的结果合格。北京市某三甲医院的测量结果显示10名放射工作人员的甲状腺¹³¹I活度均低于最小可探测活度（33.30 Bq）,济南市某三甲医院的测量结果显示4名放射工作人员的甲状腺¹³¹I活度分别为64.05 Bq、160.77 Bq、416.67 Bq、低于最小可探测活度（35.18 Bq）,4名被测对象中有3人的甲状腺内监测到¹³¹I,其对应的甲状腺待积器官剂量分别为0.70 μSv、1.77 μSv、4.58 μSv。结论 将InSpector 1000便携式γ谱仪应用于核医学科放射工作人员甲状腺¹³¹I监测的可行性强,该谱仪在辐射监测领域有很好的应用前景,可在放射防护领域、核应急现场检测领域发挥重要作用。     

50例深圳地区居民骨灰中放射性核素活度测量结果

目的 通过检测骨灰了解放射性核素在深圳地区居民体内积集的本底水平。方法 按照国家标准γ能谱仪分析,放射化学方法分析¹³⁷Cs和⁹⁰Sr。结果 50例骨灰中放射性核素活度浓度平均值为(Bq·kg^-1):²³⁸U 40.80,²³²Th 3.14²²⁶Ra 3.48,⁴⁰K 42.32,¹³⁷Cs和⁹⁰Sr未检出。结论 居民骨骼中含有微量的天然放射性核素,人工放射性核素¹³⁷Cs和⁹⁰Sr没有明显的积集,可认为当地居民骨中的内照射剂量主要来自微量的天然放射性核素⁴⁰K,²³⁸U,²²⁶Ra,²³²Th。     

Modifying effects of health status, physiological, and dosimetric factors on extrapulmonary organ distribution and excretion of inhaled plutonium in workers at the Mayak Production Association

This paper summarizes the systemic organ distribution of plutonium in workers exposed by chronic inhalation at the Mayak Production Association (MPA). Using results of radiochemical measurements in soft tissue and bone samples collected at autopsy of 853 autopsy cases, this paper provides data on the effects of various chronic diseases and malignant tumors as well as exposure time, age, sex, and body burden on systemic retention of plutonium in 22 extrapulmonary organs and on the urinary excretion rate of the nuclide. Some aspects of this work have been reported already. The results of present autopsy studies showed that liver pathology accompanied by strong fatty dystrophy of hepatocytes results in a significant relative decrease in the fraction of systemic plutonium in the liver and contravariant increase in the skeletal fraction. The average fractions of systemic plutonium in the liver and the skeleton of those MPA workers were 15% and 75%, respectively, in comparison with 47% and 45% in healthy individuals. Some of the plutonium also redistributed from the liver via blood to other systemic soft tissues. Plutonium not redistributed was excreted with urine. The results of multivariate regression analysis indicated some time-related and sex-related changes not connected with pathology for the liver and the skeleton retention fractions and excretion rate of plutonium. The current ICRP biokinetic models do not account for the influence of different pathological processes in the body on plutonium distribution in systemic organs and urinary excretion. This could have significant consequences for dosimetry calculations and risk estimations.     

Application of multi-compartment wound models to plutonium-contaminated wounds incurred by former workers at rocky flats

This paper presents the analysis of urine bioassay data, spanning four decades, from five workers who had wounds contaminated with plutonium at the Department of Energy Rocky Flats Plant during the period 1961-1967. The cases were selected from participants in the Department of Energy-sponsored Former Radiation Worker Medical Surveillance Program at Rocky Flats, which provided medical monitoring, modern bioassay measurements, and internal dose re-evaluations for former Rocky Flats workers. The cases include a variety of wound types, excision treatment regimes, and monitoring information. These wound cases illustrate the use of two multi-compartment wound models and three plutonium urine excretion models for retrospective calculation of internal plutonium depositions resulting from wounds for which no chelation therapy was administered. Wound model compartment fractions and half times are determined for each case and urine excretion model as are composite parameter values. The urine analysis and wound count measurements obtained under the program provide data with state-of-the art measurement sensitivity, as well as the opportunity to include long-term excretion and wound site data that exceed 10,000 d post-exposure for retrospective intake and dose evaluations. These data are provided to the radiation dosimetry community for use in developing and testing improved models for plutonium deposition in wounds.     

A biochemical-based model for the dosimetry of dietary organically bound tritium--Part 2: Dosimetric evaluation

In this paper the dosimetry for a novel form of physiological model, whose biokinetics are governed by the overall metabolic reactions of the principal nutrients carbohydrates, fats and proteins, is evaluated by compartmental analysis. Two models of differing complexity, called the HCNO-S and HCNO-C models, were developed from parameters evaluated in an accompanying paper. The simpler form has single compartments representing the principal nutrients. The more complex model includes compartments representing the longer-term retention of carbohydrates as glycogen, fats as adipose tissue, and proteins in bone and soft tissues. The effective doses for various tritiated intakes are the same, or similar, as calculated by the two HCNO models, except for tritiated protein. The dose coefficient for an intake of tritiated water is approximately 8% greater than that recommended by the ICRP when the tritium body burden is considered as a homogenous pool. However, when the composition of individual organs is taken into account, the dose coefficient for an HTO intake is approximately 22% greater than the ICRP value. The HCNO-C dose coefficient for OBT in a normal diet is 5.0 x 10(-11) Sv Bq(-1), which is 1.2-fold greater than the ICRP dose coefficient for an OBT intake. The HCNO-C composition model gave organ and tissue doses with the largest range for a tritiated Reference Man dietary intake, the highest dose (red marrow, then breast) being around three-fold the lowest. A property of the HCNO models, important for bioassay analyses, is that a major part (> 90%) of an OBT intake is oxidized and excreted as HTO, which is physiologically more accurate than the current ICRP OBT model. The effective dose of specific tritiated foods, e.g., rice and wheat, was evaluated on the basis of their constituents.     

Comparison of the ICRP and MIRD models for Fe metabolism in man

A task group of the Medical Internal Radiation Dose (MIRD) Committee has recently published a model of Fe metabolism in man. This model was developed to calculate doses from radioiron injected for medical diagnostic purposes. It is a compartment model with recirculating Fe exchanging between plasma and extracellular fluids, tissue storage compartments, bone marrow and red blood cells (RBC). It is a first order model with the exception of Fe in the RBC compartment, which is assumed to retain Fe for 120 days, at which time the Fe returns to the extracellular fluid compartment. By contrast, the International Commission on Radiological Protection (ICRP) model is a "once through" first order compartment model, with the compartments represented by organs (spleen, liver and other soft tissue) rather than physiological compartments as in the MIRD model. Both of these models have been implemented in the computer code GENMOD which contains the ICRP recommended lung and gastrointestinal tract models and which is used at the Chalk River Nuclear Laboratories to calculate doses, excretion rates, derived investigation levels, etc. The results of calculations using these models have been compared to see if the much less sophisticated ICRP model was adequate for radiation protection purposes. It was found that the effective dose per unit intake of radioiron was higher for the MIRD model and urinary excretion rates following an exposure were considerably different. It is concluded that the ICRP model should not be used in dosimetry calculations, or for comparing monitoring results to model calculations.     

Verification and modification of the ICRP-67 model for plutonium dose calculation

On the basis of the available data and empirical expressions for the plutonium excretion after injection, an age-related compartmental model has been developed. It provides a better agreement with measured urinary excretion data than the current ICRP 67 model. Moreover, the revised model avoids unphysiological assumptions such as the transfer of activity from soft tissue to urinary bladder, that were part of the ICRP model. The new predictions of the activity in feces and in blood after an injection are closer to the available data than the ICRP 67 estimations and there is also a good agreement with the partitioning of plutonium between skeleton and liver obtained from different autopsy studies. Furthermore, the urinary excretion estimated by the improved model has been checked using some data from occupationally exposed individuals. As the plutonium uptake in these workers occurred by inhalation, the improved model and the ICRP 67 model were compared by connecting them to the ICRP 66 respiratory tract model. The improved model consistently yields a better agreement with the measured excretion and higher estimations of intake than the ICRP 67 model.     

Implications of human tissue studies for radiation protection

Through radiochemical analysis of voluntary tissue donations, the U.S. Transuranium and Uranium Registries (USTR) are gaining improved understanding of the distribution and biokinetics of actinide elements in occupationally exposed persons. Evaluation of the first two whole-body contributions to the USTR revealed an inverse proportionality between actinide concentration and bone ash. The analysis of a whole body with significant 241Am deposition indicated a significantly shorter half-time in liver and a greater fraction resident in the skeleton than predicted by existing models. Other studies with tissues obtained at autopsy suggest that existing biokinetic models for 238Pu and 241Am and the currently accepted models and limits on intake, which use these models as their basis, may be inaccurately implying that revisions of existing safety standards may be necessary. Other studies of the registries are designed to evaluate in-vivo estimates of actinide deposition with those derived from postmortem tissue analysis, to compare results of animal experiments with human data, and to review histopathologic slides for tissue changes that might be attributable to exposure to transuranic elements. The implications of these recent findings and other work of the registries is discussed from the standpoint of this potential effect on biokinetic modeling, internal dose assessment, and safety standards and operational health physics practices.     

USTUR case 0259 whole body donation: a comprehensive test of the current ICRP models for the behavior of inhaled 238PuO2 ceramic particles. U.S. Transuranium and Uranium Registries

An analysis of 238Pu in the whole body donation to the U.S. Transuranium and Uranium Registries (USTUR) is presented. This donor accidentally inhaled an unusual physical form of plutonium, predominantly the 238Pu isotope in the form of a highly insoluble ceramic. Along with six other workers accidentally exposed at the same time, this donor excreted little or no 238Pu in his urine for several months. Subsequently, however, and, with no further intakes, the urinary excretion of 238Pu by all of these workers increased progressively. Such a pattern of increasing urinary excretion of plutonium resulting from a single acute inhalation was unknown at the time. The subject of this study provided a unique opportunity to analyze not only the pattern of urinary excretion for 17 y following this unusual intake but also the complete distribution of 238Pu in his donated body tissues and skeleton at death. Radiochemical analyses of tissues from this whole body donation were used to perform critical tests of the applicability and accuracy of the respiratory tract model and the systemic biokinetic models for plutonium currently recommended by the International Commission on Radiological Protection. The respiratory tract model was applied to analyze the donor's long-term urinary excretion pattern. The facility provided by this model to represent progressive transformation of insoluble particles in the lungs into a more soluble form, applied in conjunction with the systemic biokinetic model, predicted the total amount of 238Pu measured in the donor's body to within 17% accuracy. The measured division of 238Pu between the donor's lungs and systemic organs was predicted to within 10%. Small adjustments to several rate constants in these models provided precise predictions of the absolute amounts of 238Pu in the lungs, thoracic lymph nodes, liver, red bone marrow, skeleton (including the distribution of 238Pu between trabecular and cortical bone matrices derived from the radiochemical analyses), kidneys, testes, and muscle. The resulting individual-specific parameters were applied to evaluate the equivalent dose rates and cumulative doses received by the donor's organs and the overall effective dose. Whereas these individual modifications to the ICRP models provided a more accurate representation of the distribution of dose between the donor's organs, it was determined that the ICRP models provided an adequate estimate of the overall effective dose.