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Regional survey of indoor gamma-radiation and estimation of radiation exposure indexes in and around Vellore district, Tamil Nadu 泰米尔纳德邦Vellore区及其周边地区室内伽马辐射区域调查和辐射暴露指数估算
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_19_22
MohanDas Dinakaran, Abel Deva Krupa, R. Suriyan
The ambient gamma (γ)-radiation levels were measured in various types of dwellings in and around Vellore district. The survey was performed by using a portable Micro-R Survey Meter NUCLEONIX in different types of dwellings. The background γ-radiation exposure inside the dwelling was obtained in a total of 632 dwellings located in 30 different geographical positions in Vellore and nearby places. From the measured dose values, the radiation exposure indexes were estimated such as absorbed dose rate (ADR) and annual effective dose (AED) for the population. The present study has taken an initiative to formulate the environmental γ-radiation reference level for indoor γ-radiation level in and around Vellore district, Tamil Nadu. The calculated highest mean AED was found in concrete dwellings at 0.58 ± 0.07 mSvy−1. The highest ADR was found to be 1219 μGy/yr in tiled house. Furthermore, the work was extended to find the correlation between the temperatures, time, and type of house with radiation for a day with 2 h of regular time interval in these four types of houses and analyzed with response surface methodology.
测量了Vellore区及其周围各种类型住宅的环境伽马(γ)辐射水平。在不同类型的住宅中使用便携式微r测量仪NUCLEONIX进行了调查。住宅内的本底γ辐射暴露是在位于Vellore和附近地区30个不同地理位置的632个住宅中获得的。根据测量剂量值,估算人群的吸收剂量率(ADR)和年有效剂量(AED)等辐射暴露指标。本研究主动为泰米尔纳德邦Vellore地区及周边地区室内γ辐射水平制定了环境γ辐射参考水平。混凝土住宅的AED平均值最高,为0.58±0.07 mSvy−1。瓦房的ADR最高,为1219 μGy/yr。在此基础上,进一步研究了四种类型房屋的温度、时间和受辐射房屋类型之间的相关性,并采用响应面法进行了分析。
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引用次数: 0
Radiological assessment of natural radioactivity in building materials: The common approach 建筑材料中天然放射性的放射评估:常用方法
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_39_22
D. Rao
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引用次数: 0
Dilution factor and atmospheric dispersion pattern for Kalpakkam site Kalpakkam场地的稀释因子和大气扩散模式
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_27_22
T. Jesan, C. Manonmani, S. Ramkumar, I. Saradhi, A. Kumar
Assessment of radiological impact and for planning and preparedness programs, monthly atmospheric dispersion patterns at Kalpakkam have been studied using observed surface meteorological data during 2015–2020. The influence of meteorological factors such as wind speed, wind directions, percent of calm, atmospheric stability, and rainfall on dispersion patterns has been evaluated. The higher wind speed range (>4 m/s) is observed from 11:00 h to 19:00 h with an average wind speed of 4.17 m/s and the highest value observed in the month of May. Extremely stable F category and percent of calm observed to be lowest in the month of June. This study reveals that the high concentration area is toward seaside sectors during the southwest monsoon season from June to September and the remaining months, January to May and October to December, the most probable dispersion toward southwest, South, and North covering land sectors. Wet deposition due to maximum rainfall and more rainy days in the month of November during the northeast monsoon. The study provides site-specific information on dispersion patterns, an essential tool and crucial support for risk management with respect to radiological impact, monitoring and assessment in normal and emergency scenarios of a nuclear facility, and guiding resources for siting and design of the new facility in and around Kalpakkam.
利用2015-2020年观测到的地面气象数据,对Kalpakkam的每月大气弥散模式进行了辐射影响评估以及规划和准备方案研究。评估了风速、风向、风平浪静百分比、大气稳定性和降雨等气象因素对弥散模式的影响。11 ~ 19时风速范围较大(0 ~ 4 m/s),平均风速为4.17 m/s, 5月份风速最高。极其稳定的F级和平静的百分比在6月份被观察到最低。研究发现,西南季风季节6 - 9月的高集中区向海边分布,其余月份1 - 5月和10 - 12月的高集中区最可能向西南、南、北分布,覆盖陆地部门。在东北季候风期间,由于11月的最大降雨量和更多的雨天而导致的湿沉积。该研究提供了关于扩散模式的具体场址信息,是在核设施正常和紧急情况下进行辐射影响风险管理、监测和评估的重要工具和关键支持,并为Kalpakkam及其周围的新设施选址和设计提供指导资源。
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引用次数: 0
Estimation of evapotranspiration from measured meteorological parameters 根据实测气象参数估算蒸散量
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_13_22
R. Shrivastava, Faby Sunny, Manish Chopra, I. Iyer, R. Oza
Five empirical equations, namely, FAO-56 Penman–Monteith, Hargreaves–Samani, Makkink, Turc, and Priestley–Taylor are utilized in the estimation of evapotranspiration for the month of May in 2018 for Trombay site in Maharashtra. Evapotranspiration from a given surface is a function of incoming solar radiation, net radiation, ground heat flux, air temperature, relative humidity, and wind speed. Daily average measurements of these parameters are utilized in the empirical equations for the estimation of evapotranspiration. These estimated values are compared with the measured data from pan evaporimeter installed at Trombay. The measured data from the pan evaporimeter are corrected using the pan coefficient Kp which in turn is also estimated using empirical equations. The average value of the pan coefficient Kp is 0.8 for the site. The average measured value of evapotranspiration is 4.7 mm/d for May 2018, whereas the values estimated using the five empirical equations range from 3.3 mm/d to 12.7 mm/d. Among the five equations, the Turc equation was found to be in the best agreement with the measured values of evapotranspiration. Such studies are useful in the estimation of groundwater recharge, latent heat flux, and agriculture meteorology.
利用FAO-56 Penman-Monteith、Hargreaves-Samani、Makkink、Turc和Priestley-Taylor 5个经验方程估算了马哈拉施特拉邦Trombay站点2018年5月的蒸散量。给定地表的蒸散发是入射太阳辐射、净辐射、地面热通量、空气温度、相对湿度和风速的函数。这些参数的日平均测量值用于估算蒸散发的经验方程。这些估计值与安装在特罗姆贝的蒸发器的实测数据进行了比较。蒸发器的测量数据用蒸发器系数Kp进行了校正,而蒸发器系数Kp又用经验方程进行了估计。该站点蒸发器系数Kp的平均值为0.8。2018年5月蒸散发的平均实测值为4.7 mm/d,而使用五个经验方程估算的值范围为3.3 mm/d至12.7 mm/d。在5个方程中,Turc方程与蒸散发实测值最吻合。这些研究在地下水补给、潜热通量和农业气象学的估算中是有用的。
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引用次数: 0
Natural radioactivity content in various building materials of Chennai, Tamil Nadu, India 印度泰米尔纳德邦金奈各种建筑材料的天然放射性含量
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_14_22
K. Lakshmi, V. Meenakshisundaram, J. Punniyakotti
Natural radioactivity content in different types of building materials obtained from Chennai city has been determined. In this study, the most commonly used building materials such as clay bricks, cement, sediment, tiles, marbles, and granite have been considered for quantifying natural radioactivity content using gamma-ray spectroscopy. The annual effective dose (AED) values obtained in this study, varying from 0.04 mSv to 0.57 mSv, are deduced from the natural radioactivity content; these are lower than the European Commission Report 112 recommended level of 1 mSv. Therefore, the use of all the building materials in question, collected from in and around Chennai, in the construction of dwellings is considered to be radiologically safe for the inhabitants.
测定了从金奈市获得的不同类型建筑材料中的天然放射性含量。在这项研究中,考虑了最常用的建筑材料,如粘土砖、水泥、沉积物、瓷砖、大理石和花岗岩,以使用伽马射线光谱来量化天然放射性含量。本研究中获得的年有效剂量(AED)值从天然放射性含量推导而来,从0.04 mSv到0.57 mSv不等;这些都低于欧盟委员会报告112建议的1 mSv水平。因此,在住宅建设中使用从金奈及其周边地区收集的所有有问题的建筑材料被认为对居民来说是放射安全的。
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引用次数: 0
Studies on transfer coefficient from grass to milk for 137Cs and 40K at Kakrapar Gujarat site, India 印度Kakrapar Gujarat地区137Cs和40K牧草向牛奶转移系数的研究
Pub Date : 2022-04-01 DOI: 10.4103/rpe.rpe_25_22
S. Wagh, A. Patra, T. Jaison, I. Saradhi, A. Kumar
Transfer coefficient from grass to milk (Fm) for 137Cs and 40K was computed based on the activity measurement data in the respective matrix at Kakrapar Gujarat site, India, during 2013 - 2019. The annual geometric mean value of 137Cs activity in grass and milk samples varied from 0.13 to 0.48 Bq/kg dry wt. and 0.03 to 0.14 Bq/l, respectively. Activity observed during the year 2013 - 2019 is comparable with preoperational baseline activity level, which indicated its fallout origin. The site-specific Fm has varied between 1.0E-02 to 3.71E-02 d/l with a GM of 2.22E-02 d/l (137Cs) and between 6.69E-03 to 1.54E-02 d/l with a GM of 9.63E-03 d/l (40K), respectively. The annual effective dose due to the ingestion of 137Cs and 40K through milk consumption was found to be 0.036 μSv/y and 16.94 μSv/y, respectively. The result is an useful input for the estimation of radiation dose to human beings in accidental conditions.
2013年至2019年期间,根据印度古吉拉特邦Kakrapar工厂各自矩阵中的活性测量数据,计算了137Cs和40K的从草到奶的转移系数(Fm)。草和牛奶样品中137Cs活性的年几何平均值分别为0.13至0.48 Bq/kg干重和0.03至0.14 Bq/l。2013-2019年期间观察到的活动与术前基线活动水平相当,这表明其沉降物来源。位点特异性Fm在1.0E-02至3.71E-02 d/l之间变化,GM为2.22E-02 d/l(137Cs),在6.69E-03至1.54E-02 d/l,GM为9.63E-03 d/l(40K)。通过牛奶摄入137Cs和40K导致的年有效剂量分别为0.036μSv/y和16.94μSv/y。该结果为估计意外情况下人类的辐射剂量提供了有用的输入。
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引用次数: 0
Heavy metal contamination in water sources of Thaliparamba municipality, Kerala, India 印度喀拉拉邦Thaliparamba市水源中的重金属污染
Pub Date : 2022-01-01 DOI: 10.4103/rpe.rpe_25_21
T. Nafeesa Baby, V. Vineethkumar, K. Shimod, C. Vishnu, Sarayu Jayadevan
The present study is an attempt to assess the heavy metal contamination in the water sources of Thaliparamaba Municipality, Kannur district, Kerala. The concentration of heavy metals, namely As, Cr, Fe, Mn, Cu, Zn, Ni, Cd, Hg, and Pb in water samples was measured using X-ray fluorescence spectroscopy. The physicochemical parameters, namely pH, electrical conductivity, and salinity of the water samples were also measured. The results indicate that the concentration of most of the heavy metals in water samples collected from the study area is much higher than the permissible limits. The anthropogenic activities may influence the enhanced level of heavy metal concentration in the study area. The results of these systematic investigations are presented and discussed in detail in the manuscript.
本研究旨在评估喀拉拉邦坎努尔区Thaliparamaba市水源中的重金属污染。利用X射线荧光光谱法测定了水样中重金属As、Cr、Fe、Mn、Cu、Zn、Ni、Cd、Hg和Pb的浓度。还测量了水样的物理化学参数,即pH、电导率和盐度。结果表明,从研究区域采集的水样中,大多数重金属的浓度远高于允许限值。人为活动可能影响研究区域重金属浓度的升高。这些系统研究的结果将在手稿中详细介绍和讨论。
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引用次数: 1
Radiological assessment of petroleum products in Aniocha South Local Government Area of Delta State, South-South Nigeria 尼日利亚南南三角洲州阿尼奥查南部地方政府地区石油产品的放射性评估
Pub Date : 2022-01-01 DOI: 10.4103/rpe.rpe_5_22
B. Ijabor, A. Omojola, F. Omojola, Favour Chukwueke, Praise Azuka, Prudent Agama, Francisca Okafor
Monitoring the background levels from petroleum products is essential because of the everyday use and the increasing number of fuel, diesel, kerosene, and gas stations in Delta State, Nigeria. The study aims to determine the background ionizing radiation (BIR) in milli-Roentgen per hour (mR/h), absorbed dose rate (ADR) (nGy/h), and annual effective dose rate (AED) (mSv/year) in selected fuel, diesel, kerosene, and cooking gas-dispensing stations in Aniocha South Local Government Area of Delta State. The study was carried out using a calibrated Geiger Muller detector (Radiation Alert Inspector) in count per minute mode for point measurements and a geographical positioning system for determining the longitude and latitude of each point where measurements were taken from. The mean outdoor BIR, ADR, and AED were 0.011 ± 0.002 mR/h, 91.6 ± 19.5 nGy/h, and 0.11 ± 0.02 mSv/year, respectively, with 84% of the BIR below the world average. The mean BIR was below the world average while the ADR and AED were above it. Kerosene stations had the highest BIR. The outdoor measurements from this study were comparable to similar articles with slight variation. The study shows that the attendant and customers were safe in the areas where this study was conducted.
由于尼日利亚三角洲州的燃料、柴油、煤油和加油站的日常使用和数量不断增加,监测石油产品的本底水平至关重要。本研究旨在确定三角洲州阿尼奥查南部地方政府区选定的燃料、柴油、煤油和烹饪用汽油加气站的本底电离辐射(BIR)(单位为毫伦索每小时(mR/h))、吸收剂量率(ADR) (nGy/h)和年有效剂量率(AED) (mSv/年)。这项研究使用经过校准的盖革穆勒探测器(辐射警报检查员)以每分钟计数模式进行点测量,并使用地理定位系统确定每个测量点的经度和纬度。平均室外BIR、ADR和AED分别为0.011±0.002 mR/h、91.6±19.5 nGy/h和0.11±0.02 mSv/年,其中84%的BIR低于世界平均水平。平均BIR低于世界平均水平,ADR和AED高于世界平均水平。煤油站的BIR最高。本研究的室外测量值与类似的文章具有可比性,差异很小。研究表明,在进行这项研究的地区,服务员和顾客是安全的。
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引用次数: 0
Estimation of Fano factor for oversquare HPGe detector 过平方HPGe探测器Fano因子的估计
Pub Date : 2022-01-01 DOI: 10.4103/rpe.rpe_1_22
M. Manohari, V. Sugumar, R. Mathiyarasu, B. Venkatraman
Fano factor is a quantity used to measure the departure of the observed variance in the number of charge carriers produced from that predicted using poison statistics. Fano factor varies with the detector type. In case of proportional counters and semiconductor detectors, it is substantially less than unity, whereas, for scintillator detectors, it would be unity. Even in case of semiconductor detectors, it varies with the type and the shape of the detector. Another source of fluctuations that gives the overall resolution of the detector is preamplifier noise. Oversquare coaxial HPGe detectors are a recent development in the field. Literature on the Fano factor of oversquare large volume coaxial detector is not available. In this work, the Fano factor and the electronic noise of an oversquare HPGe coaxial detector are estimated after optimizing the shaping parameters. The Fano factor for the oversquare HPGe detector is estimated as 0.1291 keV, which agrees with the ideal value of 0.13 by 99.98%. The preamplifier noise was found to be 0.048 keV which is 35% lesser than the reported value.
法诺因子是一个用于测量观察到的电荷载流子数量变化与使用毒物统计预测的电荷载流子数变化的偏差的量。Fano因子随探测器类型而变化。在比例计数器和半导体探测器的情况下,它基本上小于单位,而对于闪烁体探测器,它将是单位。即使在半导体探测器的情况下,它也会随着探测器的类型和形状而变化。给出检测器整体分辨率的另一个波动源是前置放大器噪声。超方形同轴HPGe探测器是该领域的最新发展。关于过平方大体积同轴探测器的Fano因子的文献不可用。在本工作中,在优化成形参数后,估计了过平方HPGe同轴探测器的Fano因子和电子噪声。超平方HPGe探测器的Fano因子估计为0.1291keV,与0.13的理想值一致99.98%。前置放大器噪声为0.048keV,比报告值低35%。
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引用次数: 0
A study on the optimization of processing parameters of boron-doped CR-39 solid-state nuclear track detectors for response to thermal neutrons 掺硼CR-39固体核径迹探测器热中子响应工艺参数优化研究
Pub Date : 2022-01-01 DOI: 10.4103/rpe.rpe_28_21
Deepa Sathian, R. Pal, A. Bakshi, B. Sapra
The methodology for personnel monitoring of neutrons in the intermediate and fast energy range using CR-39 solid-state nuclear track detectors (SSNTDs) is well established. This study presents the dosimetric response of boron-doped (carborane) CR-39 detector for the measurement of thermal neutrons. It includes optimization of etching process, minimum detection limit (MDL), and thermal neutron sensitivity. Duration of low frequency (100 Hz) and high frequency (3.5 kHz) for elevated temperature electrochemical etching was optimized as 4 h and 50 minutes respectively, and used for the response characteristic study. The measured thermal neutron sensitivity and MDL were 743 ± 13 tracks cm−2 mSv−1 and 0.02 mSv, respectively. This study is useful for thermal neutron monitoring in reactor, accelerator, and all other nuclear facility environment.
利用CR-39固体核径迹探测器(SSNTDs)对中快中子进行人员监测的方法已经建立。本文研究了掺硼(碳硼烷)CR-39探测器测量热中子的剂量学响应。它包括蚀刻工艺的优化、最小检测限(MDL)和热中子灵敏度。优化低频(100 Hz)和高频(3.5 kHz)高温电化学刻蚀时间分别为4 h和50 min,并用于响应特性研究。测得的热中子灵敏度和MDL分别为743±13道径cm−2 mSv−1和0.02 mSv。本研究对反应堆、加速器及其他核设施环境中的热中子监测具有指导意义。
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引用次数: 0
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Radiation Protection and Environment
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