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1.
本文分析了新疆城市放射性废物库2012—2016年的γ剂量率、中子剂量率、表面沾污、氡浓度、土壤中放射性核素比活度以及地表水核素含量变化情况。监测结果表明:新疆城市放射性废物库库区内新库、老暂存库以及库外周围γ辐射剂量率和中子剂量率均处于乌鲁木齐市正常本底水平,表面沾污和氡浓度均未见异常,库区周围环境地表水白鸟湖总α、总β放射性浓度均低于《生活饮用水卫生标准》,土壤中γ核素均在乌鲁木齐市环境土壤天然放射性水平范围中。通过废物库的监测,对掌握新疆城市放射性废物库周边放射性水平,开展环境辐射评价提供了科学依据。  相似文献   

2.
本文报道了新疆某铀矿生产场所及周围居民村环境γ外照射水平的结果.结果表明:铀矿区生产场所γ外照射剂量率高于对照区,铀矿生产场所周围居民村环境γ外照射剂量率与对照区居民村的γ外照射剂量率相近.经估算得出了采矿、水冶工种人员和附属设施工种人员受到γ外照射最大年有效剂量当量仅为我国放射防护基本标准规定限值的9.1%和1.8%.这一附加剂量,对放射职业工作者的健康不会造成损伤影响.  相似文献   

3.
大同市环境监察支队对大同市某医院医用电子直线加速器及近距离遥控后装机工作场所及其周围环境辐射水平进行了调查。表明,加速器及近距离遥控后装机室内X、γ辐射剂量率,在关机或开机状态下监测结果变化不明显,基本在本底范围内。加速器及近距离遥控后装机室外X、γ辐射剂量率范围接近1987年“全国放射性水平调查”的天然贯穿辐射剂量平均值;屋顶X、γ辐射剂量率监测结果也居正常本底水平。  相似文献   

4.
对鄂尔多斯市涉源企业的含密封源仪表使用场所进行监测,掌握各企业的辐射防护水平,并对辐射环境进行了评价。依据《含密封源仪表的放射卫生防护要求(GBZ 125-2009)》标准,使用AT1123型X,γ辐射剂量仪对含密封源仪表5cm、100cm及环境进行γ剂量率监测,并对工作人员个人剂量计算或监测。监测的31家企业,284台含密封放射源仪表表面5cmγ剂量率范围是0.071~75μSv/h,100cmγ剂量率范围是0.058~4.400μSv/h,仪表安装环境γ剂量率范围是0.060~0.280μSv/h,厂区环境剂量γ剂量率范围是0.076~0.164μSv/h;工作人员年有效剂量值0.008~0.640mSv。监测结果表明,鄂尔多斯市含密封源仪表防护状况良好,符合国家家标准,工作人员年有效剂量值均在国家规定范围内,应加强企业辐制度建设和辐射安全管理。  相似文献   

5.
统计分析了2007—2012年的西藏原野天然γ辐射水平监测数据,与原国家环境保护局1989年开展的西藏自治区环境天然放射性水平调查研究的数据进行比较表明,2008—2012年环境连续γ辐射剂量率年均值范围为186.5~190.9 nGy/h,未见异常升高,在正常波动范围内;原野γ辐射剂量率平均值为97.9~134.0 nGy/h,测值范围为51.6~197.7 nGy/h,保持稳定状态;宇宙射线所致居民年辐射剂量为1.29 mSv/a,为内地的5倍左右,但仍属于正常水平。  相似文献   

6.
居室石材放射性监测方法探讨   总被引:2,自引:0,他引:2  
选择GB 6566- 86《建筑材料放射性卫生防护标准》及JC 51 8- 93《天然石材放射防护分类控制标准》 ,作为居室石材放射性监测依据 ,使用X γ剂量率仪对部分居室石材的放射性水平进行了现场监测 ,结果表明 :进行现场测量时 ,当X γ剂量率仪的探头质心距地面 1 0cm、测量值小于 1 2 3nGy/h± 5nGy/h时 ,可以确定该石材属于A类 ,能用于居室装饰 ;当测量值大于 1 2 3nGy/h± 5nGy/h时 ,要进一步做γ放射性比活度测量 ,以确定其放射性水平是否超标。  相似文献   

7.
厦门市区环境天然放射性水平监测   总被引:1,自引:0,他引:1  
参照国家环保局颁发的<环境天然放射性水平调查规定>,在厦门城市建城区开展了原野、道路和建筑物室内γ辐射剂量率监测,查明了市区环境的天然放射性水平现状,为厦门市放射性环境管理提供了重要的资料.  相似文献   

8.
为建立公众相关的放射性本底数据库,掌握环境介质的放射性水平和变化趋势,科学评价放射性水平及对人群健康效应的影响,新疆辐射环境监督站持续开展了对乌鲁木齐市周围环境介质放射性监测工作。本文给出了2013—2017年乌鲁木齐市气溶胶、沉降灰、土壤和地表水、饮用水中放射性核素水平以及γ瞬时剂量率和γ累计剂量的调查测量结果。调查结果表明乌鲁木齐市天然放射性水平处于本底范围内,这对掌握乌鲁木齐市放射性水平提供了科学依据。  相似文献   

9.
探讨了环境γ辐射水平的季节性变化趋势和规律,通过余弦模型对连云港田湾核电站2005—2008年度γ辐射连续监测自动站的月均值数据进行分析,并与实际值进行拟合比较,得到拟合曲线与实际曲线吻合,余弦模型能反映出γ辐射水平的季节性变化规律的结果。  相似文献   

10.
核设施外围环境γ辐射剂量率是环境保护工作中的重点监测对象。采用瞬时测量、热释光测量以及自动站连续测量3种方法分析了四川某核设施外围2011—2021年的环境γ辐射剂量率、周边居民辐射累积剂量以及这3种方法对监测结果的影响。结果表明,该核设施运行未对周围环境辐射水平造成显著影响;瞬时测量和自动站连续测量监测数据较为稳定,热释光测量易受周围环境影响造成数据波动。因此,在采用热释光测量法开展辐射环境监测时应加强对热释光剂量片布放、收取、运输、测量等环节的质量控制,并开展热释光剂量片宇宙射线响应值的测量。  相似文献   

11.
为提高四川省城市放射性废物库的安全管理水平,确保库区辐射环境安全和库内放射源实体安全,对2016—2021年四川省城市放射性废物库的库区环境监测结果进行了分析。分析表明:库区的γ辐射剂量率满足《核技术利用放射性废物贮存库选址、设计与建造技术要求》(试行)的要求,库区表面污染水平满足《电离辐射防护与辐射源安全基本标准》(GB 18871—2002)的规定,库区气溶胶历年监测数据一致性较好。此外,库区完善的安防措施为库区的安全运行提供了有力保障。四川省城市放射性废物库的运行未对库区环境造成不良影响,库区辐射环境质量良好。废物库的运行状态良好,库区辐射安全可控,其安全运行对保障全省核技术利用产业的发展和辐射环境的安全起到了重要作用。  相似文献   

12.
We estimated the return period of an increased gamma ray dose rate (Delta gamma) derived from (222)Rn progeny deposited with precipitation. The approximate probability distribution for Delta gamma followed a Hazen plot, which is an empirical plotting equation, indicating that the distribution of Delta gamma was approximated by a nearly double-exponential. The distribution of Delta gamma was well represented by the Gumbel distribution, and the return period for Delta gamma was estimated theoretically. There was a notable regional difference in the return period between the coast of the Japan Sea and the inland or Pacific coast areas: the return period for a given Delta gamma at monitoring sites on the Sea of Japan coast was 1.5 to 2.5 times shorter than that in the inland or Pacific coast areas. This variation with locality suggests that the rate of wet-deposition of (222)Rn progeny is larger at sites on the Sea of Japan coast than inland or on the Pacific coast areas. The expected return period for the maximum Delta gamma at each site was about 10 years. This estimation of the return period of Delta gamma is a novel approach to the study of environmental science in fields such as radioactivity.  相似文献   

13.
This study assesses the level of background radiation for Canakkale province of northwestern Turkey. Radon concentrations in indoor air were determined using CR-39 nuclear track detectors and 222Rn activity was found to be 167 Bq m???3 (equivalent to an annual effective dose of 4.2 mSv). Measurements of outdoor gamma radiation (of terrestrial and cosmic origin) in air were performed using plastic scintillators, and the average absorbed gamma dose rate was found to be 66.4 nGy h???1 (corresponding to an annual effective dose of 81.4 μSv). The radionuclide activity concentrations in soil samples collected from the study area were measured through gamma-ray spectrometry, and the average activities were determined as 94.55, 110.4, and 1,273 Bq kg???1 for the natural radionuclides 238U, 232Th, and 40K, respectively, and 19.39 Bq kg???1 for the fission product 137Cs. The natural radioactivity sources resulted in an annual effective dose of 184 μSv. The radioactivity levels of drinking water samples were measured as 0.0599 Bq l???1 for gross-alpha activity and 0.0841 Bq l???1 for gross-beta activity using a low-background counting technique (equivalent to an annual effective dose of 12.25 μSv). The results of this study show that the activity levels of radon in air, radionuclides in soil, and alpha activities in drinking water are higher compared to the data available for other Turkish cities and the world averages. On the other hand, the outdoor gamma dose rates in air and beta activities in drinking water are within natural limits.  相似文献   

14.
为了满足国家有关高风险移动源监管工作要求,研制了具备全球定位系统(GPS)、无线射频识别、辐射剂量监控功能的监控终端硬件,并开发设计了高风险移动源实时监控系统软件平台。对该系统平台软件和监控终端的功能及应用情况进行了分析,针对监控终端结构设计、续航时间较短、耐用性较差、野外信号弱等问题提出后续改进建议。该监控系统可以有效实现高风险移动放射源的动态监控,进一步提升江苏省高风险移动放射源的监管技术水平。  相似文献   

15.
放射源远程自动监控管理体系的构建   总被引:2,自引:0,他引:2  
以苏州的若干家放射源使用单位为例,从点位源的剂量监测、视频监控、红外报警、数据传输等方面出发,围绕提高放射源自动监控这一主题,展开了放射源远程自动监控体系的探索.  相似文献   

16.
Studies on naturally occurring radioactive material (NORM) in the limestone from the Margalla Hills have been carried out by measuring gamma activity and to access its radiological implications if any. For data acquisition, a High-Purity Germanium detector was employed. The activity concentrations of (226)Ra, (232)Th, and (40)K were found to be 14.32?±?0.24, 2.05?±?0.04, and 13.80?±?0.20 Bq kg(-1), respectively. These values are relatively lower as compared to that in the limestone of other countries and much lower than the values reported for the natural building stones. The average specific activities due to (226)Ra were found to be higher when compared with (40)K and (232)Th. Indices of radium equivalent activity (Ra(eq)), internal hazard (H(in)), indoor absorbed gamma dose rate (D(R,)), and corresponding annual effective dose (E(eff)) were also determined for the limestone-made rooms. All of these indices were found to be in the lower ranges. The Margalla Hills limestone does not pose any excessive radiological health hazard as a building material and in industrial uses for a common man.  相似文献   

17.
In this work, a numerical model is proposed to estimate air concentration of released airborne radioactive contaminants 131I and 137Cs. A Gaussian dispersion model is used to assess the atmospheric dispersion of radioactive contaminants released continuously from a nuclear power plant as a result of an accident. The model uses various input parameters such as source height, release rate, stability class, wind speed, and wind direction. The validation of the model was carried out by comparing its predicted values with published experimental data. The model was extensively tested by simulating several accidental situations. The main conclusion drawn from these tests is that for large downwind distances from the release point, the contaminant concentrations predicted by the model diverge drastically from measured data, while for short distances, the predicted values generally agree quite well with experimental data. The obtained activity concentrations range from 1.57?×?102 to 6.43?×?103 Bq/m3 for 131I and from 3.18?×?10?2 to 9.72?×?102 Bq/m3 for 137Cs. The estimated standard deviation coefficients values range of 7.2 to 6847.7 m, and the maximum absolute error predicted by the model for these parameters was less than 5%.  相似文献   

18.
The Fen Central Complex in southern Norway, a geologically well investigated area of magmatic carbonatite rocks, is assumed to be among the world largest natural reservoirs of thorium ((232)Th). These rocks, also rich in iron (Fe), niobium (Nb), uranium ((238)U) and rare earth elements (REE), were mined in several past centuries. Waste locations, giving rise to enhanced levels of both radionuclides and metals, are now situated in the area. Estimation of radionuclide and metal contamination of the environment and radiological risk assessment were done in this study. The average outdoor gamma dose rate measured in Fen, 2.71 μGy h(-1), was significantly higher than the world average dose rate of 0.059 μGy h(-1). The annual exposure dose from terrestrial gamma radiation, related to outdoor occupancy, was in the range 0.18-9.82 mSv. The total activity concentrations of (232)Th and (238)U in soil ranged from 69 to 6581 and from 49 to 130 Bq kg(-1), respectively. Enhanced concentrations were also identified for metals, arsenic (As), lead (Pb), chromium (Cr) and zinc (Zn), in the vicinity of former mining sites. Both radionuclide and heavy metal concentrations suggested leaching, mobilization and distribution from rocks into the soil. Correlation analysis indicated different origins for (232)Th and (238)U, but same or similar for (232)Th and metals As, Cr, Zn, nickel (Ni) and cadmium (Cd). The results from in situ size fractionation of water demonstrated radionuclides predominately present as colloids and low molecular mass (LMM) species, being potentially mobile and available for uptake in aquatic organisms of Norsj? Lake. Transfer factors, calculated for different plant species, showed the highest radionuclide accumulation in mosses and lichens. Uptake in trees was, as expected, lower. Relationship analysis of (232)Th and (238)U concentrations in moss and soil samples showed a significant positive linear correlation.  相似文献   

19.
The study assessed the radiological risks associated with the presence of natural and artificial radionuclides in the Bory Stobrawskie forests (PL). Using the conversion factors given by UNSCEAR and the measurements results of (232)Th series, (238)U series, (40)K, and (137)Cs specific activities in the 10-cm soil layer the values of absorbed dose (D) and the annual effective dose equivalent derived from terrestrial gamma radiation (E) were calculated. The calculated dose was compared with doses directly measured on the area studied.  相似文献   

20.
The activity concentrations of 226Ra, 232Th, and 40K in lime and gypsum samples used as building materials in Turkey were measured using gamma spectrometry. The mean activity concentrations of 226Ra, 232Th, and 40K were found to be 38 ± 16, 20 ± 9, and 156 ± 54 Bq kg???1 for lime and found to be 17 ± 6, 13 ± 5, and 429 ± 24 Bq kg???1 for gypsum, respectively. The radiological hazards due to the natural radioactivity in the samples were inferred from calculations of radium equivalent activities (Raeq), indoor absorbed dose rate in the air, the annual effective dose, and gamma and alpha indices. These radiological parameters were evaluated and compared with the internationally recommended limits. The experimental mass attenuation coefficients (μ/ρ) of the samples were determined in the energy range 81–1,332 keV. The experimental mass attenuation coefficients were compared with theoretical values obtained using XCOM. It is found that the calculated values and the experimental results are in good agreement.  相似文献   

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