新疆《煤炭资源开采天然放射性核素限量》标准评述

新疆《煤炭资源开采天然放射性核素限量》标准规定：煤炭资源天然放射线核素238铀、226Ra、23ZIh比活度豁免限量〈100Bq／k9，“限制使用”起界限量100Bq／kg，禁止开采下界量3700Bq／kg。豁免限量仅为国内外现行辐射防护标准规定大宗物料豁免限量（1Bq／g）十分之一，约为新疆已观察到土壤天然放射性核素比活度变化范围上界五分之一。《标准》在新疆实施，将有部分居民区土壤应纳入监管和控制使用范围；按国内外现行标准规定，相当数量不应监管和限制使用的煤炭资源要被纳入监管和限制使用范围；可作为铀矿资源开采的煤矿将被禁止开采，不利于新疆煤炭资源合理开发和综合利用。     

利用手持式γ核素识别仪快速检测石材中γ放射性核素含量

提出一种利用手持式γ核素识别仪快速测量石材中天然放射性核素含量的方法。该方法借助低本底HPGe γ谱仪,运用能谱分析法确定手持式核素识别仪对226Ra、232Th、40K含量的刻度系数参考值;然后使用手持式γ核素识别仪测量石材中放射性核素γ能谱,利用经过刻度系数参考值修正后的测量结果,估算出石材中226Ra、232Th、40K的比活度。结果表明:该方法测量结果与低本底HPGe γ能谱仪分析结果的最大偏差为25.1%(CRa)、-27.2%(CTh)、-15.2%(CK),可适用于快速无损的检测石材样品γ放射性比活度,以及快速估算装饰石材所致的外照射剂量。     

谈谈无机非金属建筑材料放射性测量中的技术问题

无机非金属建筑材料放射性检测的方法按《建筑材料放射性核素限量》GB6566～2001，采用低本底多通道γ能谱仪进行测量。由于标准中仅对当样品中镭226、钍232和钾40放射性比活度之和大于37Bq／kg时，测量的不确定度提出了不大于20％（扩展因子K=1）的要求：标准并未规定测量的时间，而不确定度又是髓着测量时间的长短在变化着，因此选择一个合适的测量时间，既符合测量准确度的要求，又能满足不确定度的指标，是放射性物质测量中急需解决的现实问题。     

黑龙江省主要燃煤电厂粉煤灰天然放射性水平

为了解黑龙江省主要燃煤电厂粉煤灰天然放射性核素水平及其应用情况,采用低本底HPGey谱仪对样品中天然放射性核素含量进行测量.依据国家标准GB6566-2001,对其进行比较分析,结果表明,采集的粉煤灰中天然放射性核素水平属于正常水平,属A类建筑材料,不受应用限制.     

黑龙江省主要燃煤电厂粉煤灰天然放射性水平

为了解黑龙江省主要燃煤电厂粉煤灰天然放射性核素水平及其应用情况,采用低本底HPGeγ谱仪对样品中天然放射性核素含量进行测量。依据国家标准GB6566-2001,对其进行比较分析,结果表明,采集的粉煤灰中天然放射性核素水平属于正常水平,属A类建筑材料,不受应用限制。     

建筑材料中天然放射性核素226Ra、232Th、40K比活度的测量

根据《建筑材料放射性核素限量(GB6566-2001)》标准:装修材料中天然放射性水平主要根据镭-226、钍-232和钾-40这三种核素的外照射指数和内照射指数来衡定,并规定采用低本底多道γ能谱仪进行测量。但是,γ能谱仪显示的是铀、钍、钾含量,不能直接给出放射性比活度数值,因此计算核素的内、外照射指数颇为不便。通过数学演算,得出根据放射性元素含量计算放射性比活度的计算公式,并且在实际工作中可以方便的运用。     

放射性薄层扫描仪检测用参考源研制与性能测试

采用半衰期较长、能量与PET-CT常用核素18F接近的137Cs核素,设计制作用于放射性薄层扫描仪检测的参考源,其中纯度检测参考源的活度量级为105 Bq,最小分辨距离检测参考源活度量级为104 Bq.实验表明:该参考源适用于检测放射性薄层扫描仪.检测结果显示,对于活度所占比例相差较大的样品,放射性薄层扫描仪的测量准确...     

河流沉积物环境放射性标准物质的研制

研制出一种天然基质的河流沉积物环境放射性标准物质。由多个实验室用多种准确可靠的方法对其中９种天然的和人工的放射性核素进行了定值。介绍样品制备、均匀性及稳定性检验、核素定值方法和定值结果。     

哈尔滨某电厂粉煤灰的天然放射性水平测量

为了解哈市某电厂粉煤灰中天然放射性核素水平及其应用情况,对其灰库内的粉煤灰进行取样测量,采用低本底HPGeγ能谱仪对样品中粉煤灰天然放射性核素含量进行测量。依据国家标准GB6566-2001,进行比较分析,结果表明,采集的粉煤灰中天然放射性核素水平属于正常水平,属A类建筑材料,不受应用限制。     

γ射线线性衰减系数拟合计算方法研究

线性衰减系数是放射性体源测量中进行自吸收修正的重要参数。由于能量不同,无法用人工核素点源的透射实验获得对应于天然核素发射γ射线能量的线性衰减系数值。该文提出一种新的拟合公式和拟合方法,以便由人工核素点源透射实验获得的γ射线线性衰减系数求出被测样品在天然核素γ射线能量点的线性衰减系数。对选用的5种被测物质,分别用线性衰减系数的参考值和实测值进行拟合之后的计算结果显示,在γ射线能量为60～2 600 keV的范围内,该文提出的拟合方法计算出来的线性衰减系数的最大误差分别小于4%和10%。利用该文介绍的拟合方法,可以得到被测样品在指定能量范围内比较准确的线性衰减系数值。     

Radioactivity concentration in soil samples in the southern part of the West Bank, Palestine

The activity concentrations of naturally occurring radioactive materials such as (238)U, (232)Th and (40)K were measured for 38 soil samples collected from diverse zones in the southern area of West Bank, Palestine using gamma-ray spectroscopy. The measured activities of (238)U, (232)Th and (40)K were found to range from 32.9 to 104.7, 14.5 to 76.6 and 297 to 962 Bq kg(-1) with averages value of 68.7, 48.0 and 630 Bq kg(-1), respectively. The obtained values of activity concentrations are higher than the world average of 35, 30 and 500 Bq kg(-1) for (238)U, (232)Th and (40)K, respectively. The measured (137)Cs activity concentration was found to range from 1.8 to 36.1 Bq kg(-1) with an average value of 8.5 Bq kg(-1). The detected activities were attributed to the fallout of (137)Cs, which is the only man-made radionuclide. The calculated average of the total gamma-radiation dose rate of natural radionuclides, (137)Cs and cosmic radiation is 121.4 nGy h(-1). The radium equivalent activity (R(aeq)), dose rate (D(r)), external hazard index (H(ex)) and radioactivity level index (I(gamma)) in all samples are presented. Some values were found to be in the range of worldwide values, whereas others were above the worldwide values.     

喷嘴式空气流量测量不确定度分析与评定

为了解可直接测量参数对喷嘴式空气流量测量结果准确性及可靠程度的影响,找出对测试结果影响较大的环节以进行提高测量准确度的改进,建立喷嘴式空气流量测量数学模型,分别对测试喷嘴处空气比容和测试喷嘴前后气体静压差引入的不确定度进行分析,对喷嘴式空气流量测量进行合成标准不确定度评定和扩展不确定度评定。结果表明：测试空气质量流量为0．119kg／s时,合成标准不确定度为2．396×10kg／s,扩展不确定度为1．433×10^-3kg／s,测试相对误差为1．20％,其中测试喷嘴前后气体静压差引入的不确定度较大,提出选用量程为0～500Pa的差压变送器较为适宜。     

Study on radon and radon progeny in some living rooms

In the first part of this work, the potential alpha energy concentration (PAEC) of radon progeny, the equilibrium factor (F), the activity concentration of 222Rn gas (Co) and the unattached fraction (fp), were determined in 15 living rooms at El-Minia City, Egypt. The activity size distribution of (214)Pb was measured by using a low pressure Berner impactor. Based on the parameters of that distribution the total effective dose through the human lung was evaluated by using a dosimetric model calculation of ICRP. An electrostatic precipitation method was used for the determination of 222Rn gas concentration. The mean activity concentration of 222Rn gas (Co) was found to be 123 +/- 22 Bq m(-3). A mean unattached fraction (fp) of 0.11 +/- 0.02 was obtained at a mean aerosol particle concentration (Z) of (3.0 +/- 0.21) x 10(3) cm(-3). The mean equilibrium factor (F) was determined to be 0.35 +/- 0.03. The mean PAEC was found to be 37 +/- 8.1 Bq m(-3). The activity size distribution of (214)Pb shows mean activity median diameter of 290 nm with mean geometric standard deviation (sigma) of 2.45. At a total deposition fraction of approximately 23% the total effective dose to the lung was determined to be approximately 1.2 mSv. The second part of this paper deals with a study of natural radionuclide contents of samples collected from the building materials of those rooms under investigation given in part one of this paper. Analyses were performed in Marinelli beakers with a gamma multichannel analyser provided with a NaI(Tl) detector. The samples have revealed the presence of the uranium-radium and thorium radioisotopes as well as (40)K. Nine gamma-lines of the natural radioisotopes that correspond to 212Pb, 214Pb, 214Bi, 228Ac, 40K and 208Tl were detected and measured. The activity concentrations of 226Ra, 232Th and 40K were determined with mean specific activities of 65 +/- 22, 35 +/- 12 and 150 +/- 60 Bq kg(-1), respectively. These activities amount to a radium equivalent (Ra(eq)) of 126 Bq kg(-1) and to a mean value of external hazard index of 0.34.     

A study of environmental radioactivity measurements for Cankiri, Turkey

This study is the first to assess the level of background radiation for the Cankiri province of Turkey. Indoor air radon concentrations were determined using Columbia Resin-39 nuclear track detectors and the average (222)Rn activity was found to be 44 Bq m(-3) (equivalent to an annual effective dose of 1.1 mSv). Measurements of gamma doses in outdoor air were performed using a portable plastic scintillation detector and the average gamma absorbed dose rate was found to be 8 μR h(-1) (corresponding to an annual effective dose of 87.7 μSv). Radionuclide activity concentrations in soil samples were measured through gamma-ray spectrometry and the average activities were determined as 17.7, 22.3, 357 and 4.1 Bq kg(-1) for the radionuclides (238)U, (232)Th, (40)K and (137)Cs, respectively. The average annual effective dose from the natural radioactivity sources ((238)U series, (232)Th series and (40)K) was calculated to be 44.4 μSv. Radioactivity levels of drinking water samples were carried out using a low-background proportional counter and the average gross alpha and beta activities were obtained as 0.25 and 0.26 Bq l(-1), respectively (equivalent to an annual effective dose of 184 μSv). The average radon concentrations in indoor air and the average radionuclide activities in soil were found to be lower than most Turkish cities while higher levels of outdoor gamma dose rate and water radioactivity were observed. The results of this study showed that the region's background radioactivity level differs considerably from the reported data for Turkish cities.     

Independent regulatory examination of radiation situation in the areas of spent nuclear fuel and radioactive wastes storage in the Russian far east

This paper describes the findings of the radiation situation analysis on-site near Sysoeva and Razbojnik Bays. The results of radiation monitoring performed by radiological laboratory of DalRAO and studies performed by the experts from the Burnasyan Federal Medical Biophysical Centre have been used in the course of analysis. On the industrial sites, gamma dose rate reaches 60 μSv h(-1), and the specific activities of man-made radionuclides in soil reach 2.5 × 10(4) Bq kg(-1) for (137)Cs, 7.6 × 10(3) Bq kg(-1) for (90)Sr and 2.0 × 10(3) Bq kg(-1) for (60)Co. Beyond the industrial sites, there are three local parts of the area on the coast and in the off-shore water area, contaminated with man-made radionuclides. Gamma dose rate reaches 8 μSv h(-1). The radionuclide contents in soil at this area reach 3.6 × 10(3), 2.8 × 10(3) and 19 Bq kg(-1) for (137)Сs, (90)Sr and (60)Со, respectively. At the remaining part of the area nearby Sysoeva Bay, the radiation situation complies with natural background.     

Radioactivity measurement of primordial radionuclides in and dose evaluation from marble and glazed tiles used as covering building materials in Turkey

Measurements of the natural radioactivity arising from primordial radionuclides ((226)Ra, (232)Th and (40)K) in marble and glazed tile samples used covering building materials in Turkey were carried out by gamma-ray spectrometer with a high purity germanium detector. The mean activity concentrations of the (226)Ra, (232)Th and (40)K in marble and glazed tile samples were found as 8.2, 5.5 and 58.1 Bq kg(-1) and 81.2, 65.4 and 450.1 Bq kg(-1), respectively. The radiation doses received by occupants of buildings in which the sample marble and glazed tiles might be used are estimated using measured activity concentrations of constituent primordial radionuclides and dose conversion factors evaluated by the European Commission from models of tile use. Results obtained are presented for each radionuclide, analysed and compared with relevant national and international legislation, guidance and report, and with the results obtained from other studies. Results show that the use of such decorative building materials in the construction of domestic homes or workplaces in Turkey is unlikely to lead to any significant radiation exposure to the occupants.     

Determination of specific activity of 226Ra, 232Th and 40K for assessment of environmental hazards

Studies have been carried out using gamma-spectrometric techniques to determine the natural radioactivity in some rocks that are used as building materials in Yemen. The concentrations of the natural radionuclides namely(226) Ra, (232)Th and (40)K in the rock samples collected from different rock markets in Yemen have been determined using an NaI(Tl) detector. The concentrations of (226)Ra, (232)Th and (40)K in the studied rock samples range from 22.2 to 88.8 Bq kg(-1), 8.12 to 113.68 Bq kg(-1) and 31.3 to 2222.3 Bq kg(-1), respectively. The concentrations of these radionuclides are compared with the typical world values. To evaluate the radiological hazard of the natural radioactivity, the radium equivalent activity, the air absorbed dose rate, the annual effective dose rate, the representative level index and the values of both external and internal hazard indices were evaluated and compared with the internationally approved values. The radium equivalent activity values of all rock samples are lower than the limit of 370 Bq kg(-1) except for one sample which is about 413.386. The values of external hazard index (H(ex)) and internal hazard index (H(in)), absorbed doses in indoor air and the corresponding effective dose equivalents in a typical dwelling are presented. The need for further studies is also discussed.     

Determination of gamma-emitting radionuclides in the inter-tidal sediments off Balochistan (Pakistan) Coast, Arabian Sea

Natural radionuclide contents of 226Ra, 228Ra and (40)K were studied for inter-tidal sediments collected from selected locations off the745 km long Balochistan Coast using HPGe detector based gamma-spectrometry system. The sampling zone extends from the beaches of Sonmiani (near Karachi metropolis) through Jiwani (close to the border of Iran). The natural radioactivity levels detected in various sediment samples range from 14.4 +/- 2.5 to 36.6 +/- 3.8 Bq kg(-1) for 226Ra, 9.8 +/- 1.2 to 35.2 +/- 2.0 Bq kg(-1) for (228)Ra and 144.6 +/- 9.4 to 610.5 +/- 23.9 Bq kg(-1) for (40)K. No artificial radionuclide was detected in any of the marine coastal sediment samples. 137Cs, (60)Co, 106Ru and 144Ce contents in sediment samples were below the limit of detection. The measured radioactivity levels are compared with those reported in the literature for coastal sediments in other parts of the world. The information presented in this paper will serve as the first ever local radioactivity database for the Balochistan/Makran Coastal belt of Pakistan. The presented data will also contribute to the IAEA's, Asia-Pacific Marine Radioactivity Database (ASPAMARD) and the Global Marine Radioactivity Database (GLOMARD).     

Assessment of natural radioactivity concentrations and gamma dose rate levels in Kayseri, Turkey

This study assesses the level of background radiation for Kayseri province of Turkey. Natural radionuclide activity concentrations in soil samples were determined using high-resolution gamma spectroscopy. Outdoor gamma dose measurements in air at 1 m above ground level were determined using a portable gamma scintillation detector. The obtained results of uranium and thorium series as well as potassium ((40)K) are discussed. The present data were compared with the data obtained from different areas in Turkey. From the measured gamma-ray spectra, the average activity concentrations were determined for (238)U (range from 3.91 to 794.25 Bq kg(-1)), (232)Th (range from 0.68 to 245.55 Bq kg(-1)) and (40)K (range from 23.68 to 2718.71 Bq kg(-1)). The average activity concentrations of (238)U, (232)Th and (40)K were found to be 35.51, 37.27 and 429.66 Bq kg(-1), respectively, and 11.53 Bq kg(-1) for the fission product (137)Cs. The highest values of (238)U, (232)Th and (40)K concentrations (794.25 Bq kg(-1), 245.55 Bq kg(-1), 2718.71 Bq kg(-1), respectively) were observed in abnormal samples at Hayriye village. The average outdoor gamma dose rate in air at 1 m above the ground was determined as 114.43 nGy h(-1). Using the data obtained in this study, the average annual effective dose for a person living in Kayseri was found to be about 140.34 μSv.     

An International Marine-Atmospheric 222Rn Measurement Intercomparison in Bermuda Part II: Results for the Participating Laboratories

As part of an international measurement intercomparison of instruments used to measure atmospheric ²²²Rn, four participating laboratories made nearly simultaneous measurements of ²²²Rn activity concentration in commonly sampled, ambient air over approximately a 2 week period, and three of these four laboratories participated in the measurement comparison of 14 introduced samples with known, but undisclosed (“blind”) ²²²Rn activity concentration. The exercise was conducted in Bermuda in October 1991. The ²²²Rn activity concentrations in ambient Bermudian air over the course of the intercomparison ranged from a few hundredths of a Bq · m⁻³ to about 2 Bq · m⁻³, while the standardized sample additions covered a range from approximately 2.5 Bq · m⁻³ to 35 Bq · m⁻³. The overall uncertainty in the latter concentrations was in the general range of 10 %, approximating a 3 standard deviation uncertainty interval. The results of the intercomparison indicated that two of the laboratories were within very good agreement with the standard additions, and almost within expected statistical variations. These same two laboratories, however, at lower ambient concentrations, exhibited a systematic difference with an averaged offset of roughly 0.3 Bq · m⁻³. The third laboratory participating in the measurement of standardized sample additions was systematically low by about 65 % to 70 %, with respect to the standard addition which was also confirmed in their ambient air concentration measurements. The fourth laboratory, participating in only the ambient measurement part of the intercomparison, was also systematically low by at least 40 % with respect to the first two laboratories.