浙江省天然本底辐射水平及其所致公众剂量

作者报道了浙江省天然本底辐射水平及其对公众所致的内、外照射剂量．结果表明：宇宙射线电离成分空气吸收剂量率人口加权平均值室外为３．０×１０（－８）Ｇｙ·ｈ（－１），室内为２．７×１０（－８）Ｇｙ·ｈ（－１），地表γ辐射空气吸收剂量率人口加权平均值室外为９．１×１０（－８）Ｇｙ·ｈ（－１）；室内为１４．９×１０（－８）Ｇｙ·ｈ（－１）；室内、室外空气中氡平均浓度分别为１７．２和１２．７Ｂｑ·ｍ（－３）；食品和水中天然放射性核素含量也分别进行了测定．由天然本底辐射所致公众人均年有效剂量总计为２．０ｍＳｖ，其中由宇宙射线，地表γ辐射，空气中氡、子体以及摄入天然放射性核素所致剂量分别为０．２４ｍＳｖ，０．７７ｍＳｖ，０．６７ｍＳｖ和０．３５ｍＳｖ，全省公众集体年有效剂量为８．５×１０４人·Ｓｖ．     

辽宁省公众所受电离辐射照射的基本估计

作者报告了辽宁省公众所受电离辐射照射剂量的综合结果，对其结果进行分析认为：各种主要电离辐射对公众所致的人均年有效剂量当量分别为：宇宙辐射电离成分２５１μＳｖ；地表γ辐射５３７μＳｖ；食品和水中放射性核素３１０μＳｖ；空气中氡及其子体１１６０μＳｖ；医用Ｘ射线９１．１μＳｖ；核医学１６μＳｖ；职业照射０．３９μＳｖ；放射性落下灰４６μＳｖ；燃煤放射性排出物及灰份１００μＳｖ，总计２５１１μＳｖ．各类辐射所占份额是天然辐射８９．９％（２２５８μＳｖ），医疗照射４．３％（１０７．１μＳｖ），职业照射０．０１６％（０．３９μＳｖ），放射性落下灰１．８％（４６μＳｖ），燃煤４．０％（１００μＳｖ）．     

广东大亚湾核电站运行前深圳市环境辐射水平及其所致居民剂量

目的调查广东大亚湾核电站运行前深圳市的环境辐射水平及其所致居民剂量。方法外照射调查使用ＲＳＳ－１１１高压电离室，ＦＤ－７１闪烁仪测定空气吸收剂量率或照射量率，用ＴＬＤ，ＬｉＦ（Ｍｇ，Ｃｕ，Ｐ）热释光剂量元件测定累积剂量。结果宇宙射线空气吸收剂量为２．９×１０－８Ｇｙ／ｈ，地表γ辐射空气吸收剂量率为：室外１０．８×１０－８Ｇｙ／ｈ，室内１３．４×１０－８Ｇｙ／ｈ；室内外空气中氡平均活度分别为２６．８Ｂｑ／ｍ３和１３．４Ｂｑ／ｍ３。结论由天然本底辐射所致公众人均年有效剂量约为１．６７ｍＳｖ，天然辐射所致全市公众集体年有效剂量为１．５４×１０３人·Ｓｖ·ａ－１。     

上海市1990～1994年放射工作人员外照射个人剂量水平与评价

作者提出了一种应用联合国原子辐射效应科学委员会１９８２年报告中推荐的放射工作人员个人剂量监测结果的几个参量［１］：个人年平均剂量当量、年集体剂量当量和个人剂量当量大于１５ｍＳｖ人员年集体剂量当量与总年集体剂量当量的比值ＭＲ１５的新方法。并以这种方法评价上海市放射工作人员外照射个人剂量水平。结果表明在１９９０～１９９４年期间上海市放射工作人员个人剂量［２］年平均剂量当量在０．４０～４．０４ｍＳｖ，低于国家标准所规定的剂量当量限值的十分之一（５ｍＳｖ），超过年剂量当量的十分之三（１５ｍＳｖ）有１１６人次，ＭＲ１５在０．０１～０．４９。有３２８人次超调查水平（月剂量当量限值１．２０ｍＳｖ）．对超调查水平者进行随访调查。针对＂真实＂、＂虚假＂者进行详细分析，并为有关放射工作单位提出相应的改进意见和个人防护措施。并指出今后搞好放射防护和个人剂量监测的关键［３］。     

深圳特区公共场所Rn-222浓度调查

采用固体核径迹法对深圳市公共场所氡浓度进行了调查．结果表明：室内氡浓度均值为３３．７Ｂｑ·ｍ￣（－３），公众受照剂量为０．４５ｍＳｖ，比１９８６年高０．０８ｍＳｖ。作者认为，普遍采用空调，密封式的二次装修是使氡浓度增高的主要原因．     

上海市1990—1994年放射工作人员外照射个人剂量水…

作者提出了一种应用联合国原子辐射效应科学委员会１９８２年报告中推荐的放射工作人员个人剂量监测结果的几个参量：个人年平均剂量当量、年集体剂量当量和个人剂量当量大于１５ｍＳｖ人员年集体剂量当量与总年集体剂量当量的比值ＭＲ１５的新方法。并以这种方法评价上海市放射工作个员外照射个人剂量水平。结果表明在１９９０￣１９９４年期间上海市放射工作人员个人剂量年平均剂量当量在０．４０￣４．０４ｍＳｖ，低于国家标准所     

核燃料元件运输的辐射环境影响

作者采用国际原子能机构（ＩＡＥＡ）的供的ＲＡＤＴＲＡＮ４．０程序，对核燃料运输的辐射环境影响进行了计算和分析．分析结果表明，正常运输情况下，对公众和运输工作人员所造成的集体有效剂量当量为７．９４×１０－４ｍａｎ·Ｓｖ，正常运输和运输事故对环境的影响是可接受的．     

加拿大国家剂量登记处记录的职业性辐射照射与死亡率关系的首次分析

加拿大国家剂量登记处成立于 １９５０ 年，目前有来自２４ ０００ 多个机构的超过５００ ０００ 人的包括 Ｘ 射线、γ射线、中子、β粒子、体内氚及氡子体的监测记录。方法：从 １９５１ 年１ 月 １ 日至１９８３ 年１２ 月 ３１ 日的 登记者中， 选择 记录齐 全的 ２０６ ６２０ 人（男１０５ ４５６ 人，女 １０１ １６４ 人），对其受照剂量与死亡资料作了统计分析。该人群按其职业分为４ 类：牙科工作者（占 ２１％ ）、其他医学工作者（占 ３５％ ）、工业部门工人（占 ３８％ ）及核电站工人（占 ６％ ）。以热释光剂量系统监测外照射剂量，剂量在 ０２ｍ Ｓｖ 以下者计为零。核电站报告的中子剂量的相对生物效应取为１０。通过尿样分析氚的照射并换算为以ｍ Ｓｖ 表示的剂量当量。死亡信息来自加拿大死亡资料库。对该群体随访至 １９８７ 年，平均随访 １４ 年。结果：在１９５１～１９８７ 年随访期间，共有５ ４２６ 人（男４ ２１０ 人，女 １ ２１６ 人）死亡。终生累积全身受照剂量较低：１７７ ７０３ 人在０～４９ｍ Ｓｖ，其中 ９３ ２６０ 人在 ０２ｍ Ｓｖ 以 下， 仅 １４％ 的人 累 积 剂 量 超 过１００ｍ Ｓｖ。所有成员平均剂量为 ６３ｍ Ｓｖ，而男性平均为      

用累积法对中国部分城市室内外222Rn浓度的调查

目的：为了解环境氡的变化规律和对人体的影响，从１９８８年１１月至１９９３年３月，中日合作对我国人口密集的１０个城市的室内外２２２Ｒｎ浓度进行了现场调查。方法：使用日本名古屋大学研制的Ａｌｏｋａ，Ｃｓ－２０１Ｂ型静电累积２２２Ｒｎ探测器。该仪器采样２个月时，探测下限为０，４Ｂｑ·ｍ－３。结果：室外１０个城市年平均值为８．８Ｂｑ·Ｍ－３，其中武汉市为最高（１３．５Ｂｑ·ｍ－３·ａ－１），上海的崇明岛最低（３．３Ｂｑ·ｍ－３·ａ－１）。在西北风的季节里，台湾地区室外２２２Ｒｎ浓度的５０％由陆地气团所贡献。室内１０个城市年平均值为１９．５Ｂｑ·ｍ－３，其中贵阳市最高（３３．９Ｂｑ·ｍ－３·ａ－１），上海的崇明岛最低（９．０Ｂｑ·ｍ－３·ａ－１）。１０个城市由２２２Ｒｎ及其子体所致公众年平均当量剂量为０．６４ｍＳｖ·ａ－１，其中贵阳市最高（１．１２ｍＳｖ·ａ－１），南通市最低（０．３９ｍＳｖ·ａ－１）。结论：以上结果表明，所调查的１０个城市室内２２２Ｒｎ的平均浓度值低于世界均值，２２２Ｒｎ及子体所致居民的平均剂量也低于世界均值。     

广东大亚湾核电站周围陆地环境γ辐射累积剂量水平

目的　根据广东大亚湾核电站周围环境放射性本底调查大纲对其环境放射性水平作了累积剂量调查,以积累资料。方法　采用具有补偿器的玻璃管封ＣａＳＯ４（Ｄｙ）和ＬｉＦ（ Ｍｇ,Ｃｕ,Ｐ） 热释光探测器,在大亚湾核电站陆地８０ｋｍ 范围内选定３６ 个测点,进行一年４ 次连续布放测量γ辐射累积剂量。为保证测量结果准确可靠,对所用的ＴＬＤ的性能和测读仪器均由质量保证单位进行性能检测和测读系统的考核比对。结果　大亚湾核电站周围地区环境γ辐射累积剂量率水平为：０ ～５ｋｍ 范围内为（９４－６±２８．２） μＧｙ／ｍｏ;０ ～１０ ｋｍ 范围内（８８－８ ±２５－８） μＧｙ／ｍｏ;０ ～２０ ｋｍ 范围内（８４－４±２７ ．１） μＧｙ／ｍｏ;０ ～８０ ｋｍ 范围内（８５－６ ±２５．３） μＧｙ／ｍｏ。结论　采用具有补偿器的玻璃管ＣａＳＯ４ 和ＬｉＦ（Ｍｇ,Ｃｕ,Ｐ） 探测器测定环境γ射线累积剂量辐射水平是可行的;大多数测点累积辐射水平随季节变化波动小,与用ＲＳＳ１１１１００ 高压电离室瞬时测量结果比较符合。     

Dose assessment and behavior of tritium in environmental samples around Wolsong nuclear power plant.

For the estimation of the dispersion trend of tritium discharged from the Wolsung nuclear power plant, the present level of tritium in environmental samples in the vicinity of the Wolsong site has been studied. On the basis of tritium concentrations in environmental samples, the effective dose due to tritium has been estimated for an individual and population within a 16 km radius from the Wolsong site. The annual effective dose of tritium to an inhabitant around the Wolsong site ranged from 0.15 microSv y-1 to 1.3 microSv y-1. The dose level was negligible and much lower than some applicable standards, i.e. the limit on exposure from nuclear fuel cycle to the general public as recommended by ICRP (1 mSv y-1) or US EPA's limit (0.25 mSv y-1). The collective dose to the total population within a 16 km radius from the site, 1.2 x 10(-2) man.Sv y-1 was much lower than 1 man.Sv y-1, an applicable criterion for the so-called "exemption" of radiation sources and practices from regulatory control.     

Nuclear medicine exposure in the United States, 2005-2007: preliminary results

Medical radiation exposure of the U.S. population has not been systematically evaluated for almost 25 years. In 1982, the per-capita dose was estimated to be 0.54 mSv and the collective dose 124,000 person-Sv. The preliminary estimates of the National Council on Radiation Protection and Measurements Scientific Committee 6-2 medical subgroup are that, in 2006, the per-capita dose from all medical exposure (not including radiotherapy) had increased almost 600% to 3.0 mSv and the collective dose had increased more than 700% to approximately 900,000 person-Sv. >Nuclear medicine accounted for only about 2% of all procedures but 26% of the total collective dose from diagnostic studies in medicine. In 1982, the estimated number of nuclear medicine procedures was about 7.5 million. The per-capita effective dose from nuclear medicine was 0.14 mSv and the collective dose was 32,000 person Sv. By 2005, the estimated number of procedures had increased to about 19.6 million. The per-caput effective dose increased to about 0.75 mSv and the collective dose to about 220,000 person Sv. There also has been a marked shift in the type of procedures being performed with cardiac scanning accounting for about 70% of procedures.     

Development of radiation protection standards

Radiation protection standards are based on the best available knowledge, caution, and perception. Dose limits for occupational exposure have decreased as knowledge was gained about radiation effects: from 0.6 Sv (60 rem)/year for 1900-1930 to 50 mSv (5 rem)/year in 1958 (the level still used as of 1990). Current dose limits for public exposure range from 1 mSv to 5 mSv, depending on frequency of exposure. For the embryo and fetus, dose limits are 0.5 mSv/mo and 5 mSv for the entire gestation. In the 1970s, the concept of acceptable risk and that of a non-threshold dose-response relationship became the basis for setting dose limits. Three principles of radiation protection are that (a) dose levels should not exceed acceptable levels, (b) optimal dose levels should be as low as reasonably achievable, and (c) radiation should not be used unless it produces a positive net benefit. Although no dose limits have been set for patients undergoing diagnostic and therapeutic radiologic procedures, such measures must provide a net benefit to patients at optimal dose levels.     

江苏省2011-2018年放射工作人员职业性外照射个人剂量监测结果分析

目的 了解江苏省2011-2018年放射工作人员个人剂量监测基本情况,分析其变化趋势,为保护放射工作人员健康管理提供理论基础和科学依据.方法 通过国家个人剂量登记系统,采集我省放射工作人员职业外照射个人剂量监测结果等相关数据,对其进行回顾分析.结果 2011-2018年监测江苏省放射工作人员共176 134人,总年集体...     

Radiation doses from nuclear medicine patients to an imaging technologist: relation to ICRP recommendations for pregnant workers.

The ICRP has now recommended that the dose limit to the surface of the mother's abdomen during the declared term of pregnancy is reduced to 2 mSv. Direct measurements of the radiation dose to technologists carrying out a variety of imaging studies were made. The average dose ranged from 0.3 micro Sv for a liver scan to 5.3 micro Sv for a brain scan. Using national data for the frequency of nuclear medicine studies, a weighted average figure of 1.5 micro Sv per study was derived. A technologist could therefore perform approximately eight imaging studies per day during the declared term of her pregnancy and remain within the proposed limit. Generally, there should be no need to alter a technologist's duties during her pregnancy, and these findings should be helpful in allaying any anxiety.     

Effective doses to members of the public from the diagnostic application of ionizing radiation in Germany

The exposure of the German population to man-made radiation results mainly from diagnostic X-ray and nuclear medical examinations. Data are presented about the annual frequency and the average dose of the various examination types for West Germany in the years 1990–1992. According to these data a yearly average of approximately 1550 diagnostic examinations using ionizing radiation were performed per 1000 inhabitants resulting in an annual per caput effective dose of 1.9 mSv. Despite the frequent use of alternative examination techniques, such as sonography, nuclear magnetic resonance and endoscopy, the frequency of X-ray and nuclear medical examinations is still increasing. If collective risk assessments are done using the per caput effective dose, at least the age distribution of the patients must be considered. This leads to a “risk-modifying factor“ of 0.6–0.7 for patients to be applied to the ICRP risk coefficient of 5 % per Sv valid for the general population. However, radiation risk must always be viewed in context with disease- and therapy-related risks and balanced against the benefit of the diagnostic examination, which should always exceed the risk for a well-indicated procedure. Received 12 June 1996; Revision received 21 October 1996; Accepted 8 November 1996     

湖北省2009-2018年放射工作人员职业性外照射剂量监测结果分析

目的 回顾性分析湖北省2009-2018年间放射工作人员职业性外照射个人剂量水平与分布情况,预防和控制放射性职业照射的风险.方法 以2009-2018年委托湖北省疾病预防控制中心进行个人剂量监测的放射工作人员外照射个人剂量为研究对象,共50 070人.按照相关国家标准的要求,采用热释光方法监测放射工作人员的外照射剂量当...     

UK nuclear medicine survey 2003-2004

OBJECTIVES: This survey was designed to assess the trends in the frequencies of nuclear medicine procedures in the UK and to determine their contributions to the annual collective effective dose to the UK population. The average activities administered by nuclear medicine departments were compared with guidance on diagnostic reference levels issued by the Administration of Radioactive Substances Advisory Committee. METHOD: The survey was carried out by e-mailing a questionnaire to every known nuclear medicine centre in the UK. RESULTS: The total number of procedures performed annually has increased by 36% over the last 10 years to a level of about 11 procedures per 1000 head of population in the financial year 2003-2004. Seventy-three per cent of all nuclear medicine administrations are for planar imaging, with single-photon emission computed tomography and positron emission tomography contributing 16% and 2%, respectively. Non-imaging diagnostic procedures represent 7% of all nuclear medicine administrations, and therapy 2%. Bone scans continue to be the most frequent procedure. The UK annual collective effective dose from diagnostic nuclear medicine is about 1600 man Sv, resulting in an annual per caput dose of nearly 0.03 mSv. Bone scans are the largest contributor to the collective dose, but myocardium scans are close behind. Planar imaging is responsible for 62% of the total collective effective dose from diagnostic nuclear medicine in the UK, with single-photon emission computed tomography, positron emission tomography and non-imaging contributing 33%, 5% and 0.3%, respectively. CONCLUSIONS: The practice of nuclear medicine is still expanding in the UK with single-photon emission computed tomography imaging of the myocardium rapidly approaching bone scans as the main contributor to population exposure. The activities administered for most procedures have remained substantially unchanged and adhere closely to those recommended by the Administration of Radioactive Substances Advisory Committee.     

Dose exposure in the ITALUNG trial of lung cancer screening with low-dose CT

Few data are available on the effective dose received by participants in lung cancer screening programmes with low-dose CT (LDCT). We report the collective effective dose delivered to 1406 current or former smokers enrolled in the ITALUNG trial who completed 4 annual LDCT examinations and related further investigations including follow-up LDCT, 2-[(18)F]flu-2-deoxy-d-glucose positron emission tomography (FDG-PET) or CT-guided fine needle aspiration biopsy (FNAB). Using the air CT dose index and Monte Carlo simulations on an anthropomorphic phantom, the whole-body effective dose associated with LDCT was determined for the eight CT scanners used in the trial. A value of 7 mSv was assigned to FDG-PET while the measured mean effective dose of CT-guided FNAB was 1.5 mSv. The mean collective effective dose in the 1406 subjects ranged between 8.75 and 9.36 Sv and the mean effective dose to the single subject over 4 years was between 6.2 and 6.8 mSv (range 1.7-21.5 mSv) according to the cranial-caudal length of the LDCT volume. 77.4% of the dose was owing to annual LDCT and 22.6% to further investigations. Considering the nominal risk coefficients for stochastic effects after exposure to low-dose radiation according to the National Radiological Protection Board, International Commission on Radiological Protection (ICRP) 60, ICRP103 and Biological Effects of Ionizing Radiation VII, the mean number of radiation-induced cancers ranged between 0.12 and 0.33 per 1000 subjects. The individual effective dose to participants in a 4-year lung cancer screening programme with annual LDCT is very low and about one-third of the effective dose that is associated with natural background radiation and diagnostic radiology in the same time period.     

Radon activity concentrations and effective doses in ancient Egyptian tombs of the Valley of the Kings.

Radon concentrations and equilibrium factors were measured in three pharaonic tombs during the year 1998. The tombs, which are open to the public are located in a limestone wadi on the West Bank of the River Nile at Luxor, 650 km south of Cairo. The radon activity concentration and equilibrium factor were measured monthly by two-integral nuclear track detectors (bare and diffusion detectors). Seasonal variation of radon concentrations, with summer maximum and winter minimum were observed in all tombs investigated. The yearly mean radon activity concentrations insidc the tombs ranged from 540 to 3115 Bq m(-3). The mean equilibrium factor over a year was found to be 0.25 and 0.32 inside and at the entrance, respectively. Estimated annual effective doses to tour guides ranged from 0.33 to 1.90 mSv, visitors receive doses from 0.65 to 3.80 microSv per visit. The effective dose to tomb workers did not exceed the 20 mSv yr(-1) limit.