铀矿工肺癌流行病学调查研究

调查分析了５个铀矿１３３６０名男性职工中癌死亡。观察期自１９７１年１月至１９８５年１２月。肺癌死亡３５名，放射组２４名，对照组１１名．两组肺癌标化死亡率分别为２１．４２×１０－５（放）１５．９４×１０－５（对）．标准死亡比（ＳＭＲ）分别为１·８３（放）和１．４４（对）。放射组标准死亡比有显著意义。放射组肺癌相对危险系数为１．０７％·ＷＬＭ－１。     

核工业职工死因危险及相关职业危害的分析

目的在核工业职工全死因调查的基础上，着重进行死因危险及相关职业危害的分析，探讨职业与健康的关系。方法调查对象为１１个单位自组建至１９９０年底在册职工，分组观察。调查历年职工人数及死亡资料，按ＩＣＤ－９原则进行死因统计。结果粗死亡率１９３．６６×１０－５，标化死亡率２３７．６５×１０－５，而放射组、非放射组分别为３４６．１１×１０－５、２０２．０３×１０－５（Ｐ＜０．０１），但均低于全国值。放射组与非放射组比较，ＲＲ１．７０（Ｐ＜０．０１），但去除矽肺和工伤死亡，ＲＲ１．３０（Ｐ＞０．０５）。肿瘤居死因之首，第二为损伤与中毒。全死因ＳＭＲ０．４６，肿瘤０．７６，而损伤与中毒１．２０（Ｐ＜０．０１）；肺癌１．４０（Ｐ＜０．０１）；脑瘤１．５１（Ｐ＜０．０５）；铀矿系统肺癌、脑瘤、胃癌、肝癌、白血病增加明显。结论与死亡相关的职业危害为粉尘、工业外伤和氡子体，放射组死因危险因此增高，但情况在不断变化。男性比女性有更多死因危险，铀矿工肺癌与氡子体暴露有关。     

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．     

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。     

包钢含钍粉作业工人恶性肿瘤死亡队列研究

为了弄清吸含钍粉尘是否可导致恶性肿瘤死亡率的增加，我们对包钢的全部接触粉尘者进行了１７年的全死因队列调查，累积１１１２８６人年，其中暴露组成员占７４８２７人年，平均肺累积剂量２１．７ｍＳｖ，累积γ照射剂量当量在０．０１－７５ｍＳｖ之间，全死因分析结果：恶性肿瘤占第一位死因，白血病和肺癌的ＲＲ分别是６．１３是１．２４，Ｐ＞０．０５；ＳＭＲ分别是３．０６和１．５５。经剂量分组分析未发现它们的８增加与中     

包钢含钍粉尘作业工人恶性肿瘤死亡队列研究

为了弄清吸入含钍粉尘是否可导致恶性肿瘤死亡率的增加，我们对包钢的全部接触粉尘者进行了１７年的全死因队列调查．累积１１１２８６人年，其中暴露组成员占７４８２７人年，平均肺累积剂量２１．７ｍＳｖ，累积γ照射剂量当量在０．０１～７５ｍＳｖ之间．全死因分析结果：恶性肿瘤占第一位死因，白血病和肺癌的ＲＲ分别是６．１３和１．２４，Ｐ＞０．０５；ＳＭＲ分别是３．０６（Ｐ＜０．０５）和１．５５（Ｐ＞０．０５）．经剂量分组分析未发现它们的增加与吸入钍尘或γ外照射有关联．肺癌的增加与吸烟有关，白血病死亡率的增加可能存在着除辐射以外的其它诱发因素，有待进一步探讨．     

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。     

核工业职工在危险及相关职业危害的分析

目的 在核工业职工全死因调查的基础上，着重进行死因危险及相关职业危害的分析，探讨职业与健康的关系。方法 调查对象为１１个单位自组建至１９９０年底在册职工、分组观察。调查历年职工人数及死亡资料，按ＩＣＤ－９原则进行死因统计。结果 粗死亡率１９３．６６×１０＾－５，标化死亡率２３７．６５×１０＾－５，而放射组、非放射组分别为３４６．１１×１０＾－５、２０２．０３×１０＾－５，但均低于全国值。放射组与非     

阳江高本底辐射地区的个人外照射剂量估算和人员的剂量分组

目的为了更好地进行剂量与效应关系的分析,将高本底辐射地区（ＨＢＲＡ）的人员按村平均的环境γ外照射水平及各自的居留因子估算的村平均有效剂量分成“高”、“中”、“低”三个剂量组和相邻的正常本底地区（ＣＡ）的一个对照组。方法在进行辐射剂量与效应关系的研究时,采用环境γ外照射辐射水平（卧室、室内、外和田野）的测量和个人累积剂量（ＴＬＤ）的两种测量方法给出ＨＢＲＡ和ＣＡ各组人员平均有效剂量。结果这两种方法的测量结果：ＨＢＲＡ分别是２１１８６×１０－５Ｓｖ·ａ－１和２０６７５×１０－５Ｓｖ·ａ－１;ＣＡ分别是６８６０×１０－５Ｓｖ·ａ－１和６７１１×１０－５Ｓｖ·ａ－１。两种不同测量方法所估算的村平均有效剂量有很好的相关性,它们的直线回归方程为Ｙ＝０．９３３７Ｘ＋６．０４４４,相关系数ｒ＝０．９９４９。结论环境γ外照射辐射水平测量方法的总的不确定度为１５％。作者分析了引起人员误分组的原因,并认为人员的误分组的可能性不会超过１％,它不会影响分组作用的有效性。     

甘肃某矿区周围居民恶性肿瘤死亡调查

目的 评价核设施在正常运行50年后对周围人群的健康影响.方法 调查甘肃某矿区周围30 km范围内居民2004-2008年人口资料、全部实体癌和白血病的死亡率.结果 调查地区居民2004-2008年全癌死亡率和标化死亡率分别为95.51/105和93.56/105,白血病死亡率和标化死亡率分别为2.44/105和2.22/105.对照区2004--2008年间恶性肿瘤死亡率和标化死亡率分别为106.88/105和89.31/105,白血病仅死亡1例,死亡率为3.56/105.结论 甘肃某矿区运行50年后,周围居民的恶性肿瘤和白血病死亡率未见增加,该矿区的生产和运行未对周围居民健康造成不良影响.

Abstract：

Objective To evaluate the cancer risk among the inhabitants around a certain nuclear facility of Gansu Province after operation for nearly 50 years.Methods Specially developed forms were filled by countryside doctors in the villages 30 km on the leeward or at the lower reaches of Yumen City,Gansu Province where a nuclear facility had operated for nearly 50 years,to register the relevant data of those who died of solid cancer and leukemia during the period from 1 January 2004 to 31 December 2008 based on the relevant data and household survey.A town 90 km away from the nuclear facility with 4181 people were regarded as control area.Results The crude mortality and standardized mortality rate(SMR) of cancer were 95.51×10-5 and 93.56×10-5.respectively.The crude mortality and SMR of leukemia were 2.44×10-05 and 2.22×10-05, respectively.and the crude mortality and SMR of cancer were 106.88×10-05, and 89.31×10-5, respectively.The crude mortality and SMR of leukemia were 2.44×10-05 and 2.22×10-5, respectively in the investigated area,and the crude mortality of leukemia was 3.56×10-5 (only one leukemia cage died)in the control area in the same time.The cancer and leukemia mortality rates of the investigated area were similar to those of control area.Conclusions Nuclear facility does not significantly increase the cancer mortality among the residents living nearby.     

2006-2009年瓦房店市红沿河核电站周围居民恶性肿瘤死亡基线调查

目的 对红沿河核电站运行前瓦房店市居民恶性肿瘤死亡情况进行基线调查,为核电站的正常运行及核事故对健康影响的评价提供科学依据.方法 瓦房店市30个乡镇按照距离核电站0、10、20、30和40 km外分成5个调查区域进行分析,分析不同区域、不同性别、不同年龄恶性肿瘤的死亡分布.选取对辐射敏感的恶性肿瘤(白血病、乳腺癌和甲状...     

湖南A铀矿氡和氡子体及矿工肺癌

本文分析了湖南A铀矿井下氡子体对矿工的危害。早年井下氡和氡子体浓度超过限值20多倍.自建矿至1985年底, 主要工种的氡子体累积暴露量平均200WLM。观察2149名1971年前下井老工人, 1970～1985(15年)肺癌死亡11例, 肺癌粗死亡率35.14×10^-5, 特异死亡率24.07×10^-5, SMR=3.17。肺癌平均井下工龄18.5年。肺癌绝对危险系数5.58×lO^-6人年·wLM^-3, 特异相对危险系数5.03×l0^-2WLM^-1。剂量效应分析表明, 肺癌危硷随氡子体累积暴露量增加而增高。     

质子加速器放射治疗场所活化核素所致人员受照剂量估算与分析

目的 了解质子加速器放射治疗场所空气活化产物可能致工作人员的受照剂量水平,为治疗场所的防护设计和人员的放射防护提供技术基础。方法 以PROTEUS235型质子治疗系统为例,分析质子加速器运行时场所空气中可能产生的主要活化核素,估算工作场所内活化核素的放射性活度浓度及其所致人员的受照剂量。结果 在质子加速器厅内,活化核素¹⁵O的放射性活度浓度最高,为4.1×10^-2Bq ·cm^-3;¹³N、⁴¹Ar和¹¹C依次为3.3×10^-2、6.2×10^-3和2.0×10^-2Bq ·cm^-3。在质子束治疗室内,上述核素放射性活度浓度约为加速器厅内的5%。工作人员在停束后5和30 min进入质子加速器厅内,因外照射可能受到的年有效剂量分别小于1和0.1 mSv;在质子治疗停束后即刻进入治疗室,因空气活化所致年有效剂量为1.3～2.0 mSv,而在停束后5和15 min进入时分别为0.7～1.2和0.3～0.6 mSv。结论 质子加速器治疗场所空气中活化核素所致人员受照剂量不容忽视,应主要考虑活化核素¹⁵O、¹³N、⁴¹Ar、¹¹C所致外照射对工作人员造成的剂量贡献,并采取必要的防护措施。     

核电站周边地表水中铀的同位素丰度分析

目的 掌握核电站周边地区地表水中铀同位素丰度比值基线数据.方法 采集江苏、山东、浙江省境内3个核电站周边地区供饮用的地表水,利用磷酸三丁酯(TBP)萃淋树脂分离富集铀,电感耦合等离子体质谱(ICP-MS)法分析样品中的234 U/238U与235 U/238U的丰度比.结果 地表水中234 U/238U丰度比范围为4.575×10-5 ～7.752×10-5,235 U/238U丰度比范围为7.273 ×10-3～7.639×10-3.结论 地表水中234U被不同程度地富集.     

Dosimetry of transmission measurements in nuclear medicine: a study using anthropomorphic phantoms and thermoluminescent dosimeters

Quantification in positron emission tomography (PET) and single photon emission tomographic (SPET) relies on attenuation correction which is generally obtained with an additional transmission measurement. Therefore, the evaluation of the radiation doses received by patients needs to include the contribution of transmission procedures in SPET (SPET-TM) and PET (PET-TM). In this work we have measured these doses for both PET-TM and SPET-TM. PET-TM was performed on an ECAT EXACT HR+ (CTI/Siemens) equipped with three rod sources of germanium-68 (380 MBq total) and extended septa. SPET-TM was performed on a DST (SMV) equipped with two collimated line sources of gadolinium-153 (4 GBq total). Two anthropomorphic phantoms representing a human head and a human torso, were used to estimate the doses absorbed in typical cardiac and brain transmission studies. Measurements were made with thermoluminescent dosimeters (TLDs, consisting of lithium fluoride) having characteristics suitable for dosimetry investigations in nuclear medicine. Sets of TLDs were placed inside small plastic bags and then attached to different organs of the phantoms (at least two TLDs were assigned to a given organ). Before and after irradiation the TLDs were placed in a 2.5-cm-thick lead container to prevent exposure from occasional sources. Ambient radiation was monitored and taken into account in calculations. Transmission scans were performed for more than 12 h in each case to decrease statistical noise fluctuations. The doses absorbed by each organ were calculated by averaging the values obtained for each corresponding TLD. These values were used to evaluate the effective dose (ED) following guidelines described in ICRP report number 60. The estimated ED values for cardiac acquisitions were 7.7×10^–4±0.4×10^–4 mSv/MBq · h and 1.9×10^–6±0.4×10^–6 ███/MBq · h for PET-TM and SPET-TM. respectively. For brain scans, the values of ED were calculated as 2.7×10^–4±0.2×10^–4 mSv/MBq · h for PET-TM and 5.2×10^–7±2.3×10^–7 mSv/MBq · h for SPET-TM. In our institution, PET-TM is usually performed for 15 min prior to emission. SPET-TM is performed simultaneously with emission and usually lasts 30 and 15 min for brain and cardiac acquisitions respectively. Under these conditions ED values, estimated for typical source activities at delivery time (22000 MBq in SPET and 555 MBq for PET), were 1.1×10^–1± 0.1×10^–1 mSv and 1.1×10^–2±0.2×10^–2 mSv for cardiac PET-TM and SPET-TM respectively. For brain acquisitions, the ED values obtained under the same conditions were 3.7×10^–2±0.3×10^–2 mSv and 5.8×10^–3±2.6×10^–3███ for PET-TM and SPET-TM respectively. These measurements show that the dose received by a patient during a transmission scan adds little to the typical dose received in a routine nuclear medicine procedure. Radiation dose, therefore, does not represent a limit to the generalised use of transmission measurements in clinical SPET or PET. Received 12 May and in revised form 1 July 1998     

接触131I放射性核素工作人员内照射剂量估算方法的初步研究

目的 探索接触¹³¹I放射性核素放射工作人员内照射剂量估算方法。方法 选择某¹³¹I放射性药物生产企业和某开展¹³¹I甲亢和甲状腺癌治疗的医院核医学科放射工作人员,使用便携式高纯锗（HPGe）γ谱仪,以7 d为周期,连续4次测量甲状腺部位¹³¹I活度,结合人员接触¹³¹I的轮岗方式,估算内照射剂量。结果 以监测月份为典型月份估算人员内照射剂量时,调查企业从事¹³¹I放射性药物分装的生产人员年待积有效剂量为0.09~1.93 mSv,调查医院核医学科工作人员内照射年待积有效剂量为0.06~0.58 mSv。对监测结果进行校正和结合轮岗方式后估算的工作人员内照射年待积有效剂量,放射性药物生产工作人员和核医学科工作人员分别为0.06~1.22 mSv和0.03~0.16 mSv。结论 在进行接触¹³¹I放射性核素工作人员内照射剂量估算时,仅以单次测量的结果估算全年受照剂量会带来较大的误差。在连续监测时,应根据前续监测周期的结果对后续监测周期结果进行校正。为准确估算人员内照射剂量,应充分考虑工作人员接触¹³¹I的方式、接触的时间、接触的频率、内污染的途径等因素。对于接触¹³¹I内照射剂量可能>1 mSv/年的工作人员,以14 d作为常规监测周期较为适宜。     

Overview of Radiation-induced Skin Cancer in Humans

Summary

There are about a dozen studies of the incidence of skin cancer among irradiated populations with known skin doses that are available for estimating the risk of radiation-induced skin cancer. It is of note that they provide no evidence for a dose threshold and are compatible with a linear dose–response relationship, at least for ultraviolet radiation exposed skin. The studies also provide varying amounts of evidence concerning a number of other important issues in assessing skin cancer risk: types of skin cancer induced by ionizing radiation, the appropriateness of relative risk vs absolute risk models, combined effects of ionizing and UV radiations, and variations in sensitivity to skin cancer induction among demographic and genetic subgroups. Little epidemiological information is available on several factors, such as the RBE for high-LET radiation, the effects of dose protraction or fractionation, or variations in risk by age at irradiation. A reasonable estimate of skin cancer lethality was 0·2 per cent when weighted for the relative proportions of squamous cell and basal cell skin cancers. Average risk estimates of radiation-induced skin cancer incidence were: absolute risk (AR) of 8·5 × 10^?4 person-year-Sv and excess relative risk (RR) of 52 per cent/Sv. Lifetime skin cancer risk was calculated by life-table methods for males from exposures spread out over ages 20–60 years. The estimates for excess skin cancer incidence were 2 per cent and 11 per cent per Sv under the AR and RR models, respectively, while the corresponding mortality risks were 4 × 10^?5 and 2 × 10^?4 per Sv.     

福清市2007—2009年居民恶性肿瘤发病与死亡特征调查

目的：调查福建省福清核电站核设施运行之前当地居民恶性肿瘤发病与死亡分布特征。方法：回顾性调查福清市2007—2009年居民恶性肿瘤发病与死亡,分析恶性肿瘤以及与核辐射相关的主要恶性肿瘤发病与死亡分布特征。结果：福清市2007—2009年居民恶性肿瘤发病率148.65/10万,死亡率114.96/10万;肝癌、胃癌、肺癌、食管癌和结直肠癌是前5位恶性肿瘤;白血病发病率3.77/10万,死亡率2.61/10万,甲状腺癌发病率6.95/10万,死亡率0.46/10万。结论：核电站运行之前,福清市恶性肿瘤以消化系肿瘤和肺癌为主;白血病发病率与死亡率低于全国平均水平,甲状腺癌发病率与死亡率高于全国平均水平。该地区应持续开展恶性肿瘤发病与死因监测,以评估核电站运行对人群健康的影响。     

Occupational exposure to ionizing radiation has no effect on T‐ and B‐cell total counts or percentages of helper,cytotoxic and activated T‐cell subsets in the peripheral circulation of male radiation workers

Purpose: To investigate changes in immune cell subsets in the peripheral circulation of a male population occupationally exposed to ionizing radiation.

Materials and methods: Peripheral blood samples were taken from 194 male workers with cumulative exposures of >200?mSv (mean exposure 331.5?mSv, mean age 51 years) and from a reference population of 131 male workers with cumulative exposures of <27.5?mSv (mean exposure 13.9?mSv, mean age 47 years). Samples were analysed by flow cytometry for T‐ and B‐cell total counts and for the T‐cell subset percentages of CD4⁺ (helper T‐cells), CD8⁺ (cytotoxic T‐cells) and CD3⁺/HLA‐DR⁺ (activated T‐cells).

Results: Comparison of the >200 and <27.5?mSv exposure groups using linear regression analysis showed no statistically significant differences between the two groups for T‐cell total count, B‐cell total count or for percentages of the T‐cell subsets CD4⁺, CD8⁺ or CD3⁺/HLA‐DR⁺ and CD4⁺:CD8⁺. However, statistically significant increases in both T‐ and B‐cell total counts were observed within the two exposure groups and data pooled from both groups when non‐smokers (never and ex‐smokers) were compared with current smokers. For pooled data T‐cell total count increased in smokers by 35% (p=0.0001) and B‐cell total count increased by 37% (p=0.0004).

Conclusions: No significant immunological effects were observed in male radiation workers with cumulative exposures of >200?mSv when compared with a reference population with cumulative exposures of <27.5?mSv, although highly significant increases in both T‐ and B‐cell total counts were observed in smokers compared with non‐smokers.