克量粉末样品中低比活度放射性核素的γ能谱分析

报道了缺少小直径圆盘状体标准源条件下,快速简便地测定固体粉末样品中多种人工放射性核素比活度的γ能谱分析方法。取1g左右样品,装在特制的塑料盒中,形成Φ26mm×3mm的小圆盘状。由于样品的比活度较低,采用低源距(1cm,记为H1)测量。由于没有与样品圆盒相同形式的体标准源,利用直径26mm的60Co平面标准源在高源距(25cm,记为H25)测定若干放射性核素平面源的活度及峰效率,再测定H1的平面源峰效率。然后源距在H1基础上逐次增加1mm以测量平面源的峰效率,拟合峰效率随距离变化的函数,模拟得到厚度为3mm圆盘体标准源的峰效率。最终测定了样品比活度(包含自吸收校正)。与样品中两种核素的放化分析结果比对,测定结果偏差≤4%。     

大面积~(90)Sr-~(90)Yβ源制备方法研究

采用自制大面积平面源制备装置,研究了电镀时间、电压、溶液酸度、极间距、阳极移动速度等参数对90Sr-90 Y电镀效率的影响,得到了较佳的工艺参数,电镀效率大于85%。利用该参数成功制备了300cm2(13cm×24cm)、600cm2(15cm×38cm)、1 000cm2(25cm×38cm)等不同活性区面积的90Sr-90 Yβ源。结果表明,所制得的90Sr-90 Yβ源均匀性好于10%,擦拭实验证明牢固性可靠。本方法可用于制备大面积α、β标准平面源,以满足大面积表面沾污仪等仪器设备的检定、校准。     

放射性氙测量中的天然源γ谱仪校准技术

基于禁核试核查现场视察的需求,研制了用于放射性氙测量的模拟气体源,实现了¹³³Xe 81.0 keV γ射线的效率校准。放射源基质为聚苯乙烯泡沫颗粒,母体核素为²²⁶Ra,采用不锈钢外壳封装,同时采用碳纤维窗以减少射线的衰减。放射源研制完成后,对其进行气密性和均匀性检验。当放射源达到平衡后,测量²¹⁴Pb的特征X射线的探测效率,然后插值计算得到¹³³Xe 81.0 keV γ射线的探测效率。为检验校准结果的正确性,制作了一个基质和几何尺寸均与²²⁶Ra源相同的¹⁵⁵Eu放射源,并在相同测量条件进行了实验。结果表明,¹⁵⁵Eu 86.5 keV γ射线和²¹⁴Pb 87.3 keV X射线的探测效率之间的相对偏差小于1.0%。     

模拟气体标准源法校准反应堆惰性气体监测仪效率

为准确校准惰性气体监测仪对气体源的γ射线全能峰效率,制备了以可发性聚苯乙烯（EPS）颗粒为基质材料的马林杯放射性模拟气体标准源,模拟气体标准源装样密度为4.1 kg/m³,其中含²⁴¹Am、¹⁰⁹Cd、⁵⁷Co、⁵¹Cr等8种单能γ射线发射核素。利用该模拟气体标准源,对反应堆惰性气体现场监测仪的HPGe探测器γ射线全能峰效率进行了校准,校准覆盖能区为60～1836 keV,校准的效率标准不确定度最大为4.4%。同时采用点源代表点法进行了效率校准,并将模拟气体标准源与代表点位置处的点源效率校准结果进行对比,发现在校准能区内二者的效率比不为常数,效率偏差最大达28%,通过效率传递系数可减小偏差,且可得到效率传递系数拟合曲线。最后在81 keV能量点处,得到模拟气体标准源与标准气体源的效率比为1.26,此值可作为模拟气体标准源的实际应用参考。     

放射性核素γ谱分析方法探讨

在实验室仅存在混合刻度源条件下,探讨不同解谱方法对放射性核素活度估算的适用性。本文利用HPGe γ谱仪测量样品,并分别采用效率曲线法和相对比较法来分析样品中~(241)Am、~(60)Co、~(137)Cs、~(40)K核素活度。结果表明,若干扰核素对样品中待分析核素产生的影响可忽略,但对混合刻度源中相应的待分析核素影响较大时,经综合考虑,相对比较法所得结果优于效率曲线法;若干扰核素对样品中待分析核素产生的影响不可忽略,但对混合刻度源中相应的待分析核素影响不大时,与相对比较法相比,效率曲线法占优势。     

Dependence of Position Signal on Pressure of Counting Gas in Charge Division Type Position-Sensitive Proportional Counter

In the absolute radioactivity measurement of radioisotope gaseous samples with newly developed position-sensitive proportional counter (PSPC) method, it is necessary to change the counting gas pressure for the correction of the wall effect. The position signal was found to drift depending on the pressure. Theoretical explanation was given for this drift. Rise time of output pulses varies with gas pressure, which leads to a change of ballistic deficit. Consequently, the ballistic deficit differs between pulses from both the ends of the PSPC, which causes the change of position signals. Increasing the pressure of the counting gas from 0.5×10⁵Pa to 4×10⁵Pa, the range of position signals for two position calibration sources became narrower by about 8% under 6 μs shaping time.     

HPGe探测器对圆柱型体γ源效率刻度的经验公式

介绍了HPGeγ探测器的圆柱型体源效率刻度的经验公式。利用单能量γ射线放射性源141Ce(145.4keV)、51Cr(320.8keV)、198Au(411keV)、65Zn(1115.5keV)的水介质体源对经验公式进行了检验。结果表明,用经验公式计算的相对效率与实验结果的相对偏差在5%以内,证明了该公式的实用性。     

基于三角圆筒铅屏蔽NaI探测器的放射源定位研究

随着放射源和放射装置的广泛应用,放射源事故的发生概率不断增大。因此,一旦发现放射源丢失,如何尽快将其定位并安全找回尤为重要。本文设计了一种三角圆筒铅屏蔽的NaI探测器,用于放射源的定位探测。实验研究了测量时间、铅屏蔽厚度、源与探测器间距、伽马射线能量等因素对放射源定位的影响。结果表明:对于137 Cs源,在空气吸收剂量率≥0.028μGy/h处,定位平均角度偏差≤1.24°;对于60 Co源,在空气吸收剂量率0.4μGy/h处,测量的平均角度偏差为1.16°;对于距离约1.5 m的9.25×105 Bq 137 Cs源,定位偏差约为0.097m。     

β-γ符合效率外推法绝对测量133Xe活度

放射性气体氙监测是全面禁止核试验条约国际监测系统关注的重点之一,准确测量放射性气体氙活度是其中的难点。本文详细介绍了β-γ符合效率外推法测量放射性核素活度的原理和方法,并绝对测量了¹³³Xe活度。结果表明,β-γ符合效率外推法作为一准确度较高的放射性核素活度绝对测量方法,可应用于气体放射性核素的活度测量;为提高测量准确度,可通过减小气体自吸收效应提高β探测效率。     

平板高纯锗探测器几何参数修正的解析方法

本文推导了1个用于计算平板高纯锗探测器对点源发射光子的探测效率的数值积分公式,并应用此积分公式进行了高纯锗探测器的几何参数修正。将²⁴¹Am、¹³⁷Cs点源分别置于平板探测器前端的不同距离（1~20 cm）处进行实验测量,以探测效率的实验结果为拟合真值,利用积分公式通过加权最小二乘拟合获得该探测器的几何参数。将修正后的参数应用于MCNP模拟计算,对59.5及661.6 keV光子,在1~20 cm探测距离范围内,探测效率的模拟值与实验值之间的相对偏差<1%。研究表明,此解析方法实现了对探测器几何参数的快速修正,结果准确可靠。     

ISOCS系统无源效率刻度测量方法的准确性检验

以比较的方法,介绍了ISOCS系统无源刻度测量方法相对于传统环境样品放射性测量方法的优点,采用ISOCS系统无源刻度测量方法对环境标准土壤样品进行了测量,结果表明,ISOCS系统无源效率刻度测量方法是测量环境样品放射性的快捷、可靠的方法。     

双探测位置分段γ扫描系统研究

本文以双探测位置的分段γ扫描技术为基础,建立了环放射源探测效率的理论计算方法,其能根据放射源所处的实际位置实时计算出探测效率。在此基础上研发了一套探测系统,实现了对废物桶的自动化探测。使用该系统对单个及多个60 Co和137 Cs及聚氨酯和木头组成的模拟桶进行测量。测量单个及多个放射源活度相对误差平均值分别为10%和7.9%,优于使用传统分段γ扫描技术的探测结果,最后根据测量环境估算了探测系统的最小探测限。     

大流量气溶胶滤膜标准γ体源制备技术

为制备大流量气溶胶滤膜标准γ体源,采用参数优化的专用滴源装置,将放射性标准溶液⁶⁰Co定量滴注在气溶胶取样滤膜上,晾干后对角折叠,并采用专用压样装置压制成与测量样品几何形状一致、密实的圆盘形固态物,密封保存。采用差重法对制备的滤膜标准γ源进行活度定值,制备的气溶胶滤膜标准γ体源活度值为4.4×10⁴ Bq,相对扩展不确定度U（k=2）为3.6%。采用分割压制法对气溶胶滤膜标准γ体源进行均匀性测量,相对标准偏差低于5%。制备的滤膜标准γ源可为测量大流量气溶胶样品的γ谱仪效率刻度服务。     

Verification of modified sum-peak method in Monte Carlo simulationof full energy peak and sum-peak efficiencies of a HPGe detector

The modified sum-peak method estimates radioactivity by using only the peak and the sum-peak count rates.To verify the modified sum-peak method,the dependence of the full energy peak efficiency on the source-to-detector distance in a high-purity germanium detector system was studied using a Geant4 Monte Carlo simulation.The effect of the deadlayer in the germanium crystal was estimated by reference to experiments on ²⁴¹Am and the relative efficiency of the detector.The peak efficiency...     

Precise Intensity Measurements in the 14N(n, γ)15N Reaction as a γ-Ray Intensity Standard up to 11MeV

The main γ-ray intensities in the ¹⁴N(n, γ)¹⁵N reaction were determined at an accuracy of 0.3–1.0% based on the intensity balance principle. Measurements were performed at the supermirror neutron guide tube at the Kyoto University reactor (KUR). A liquid nitrogen target and a deuterated melamine (C₃D₆N₆) one were used. We prepared a full-energy-peak efficiency curve by combining the measured and calculated efficiency curves. The previous values widely used as intensity standards agreed with the present results within 4–5% in the 2–11 MeV region, but the ratio to the present values showed a monotonic decrease with the increase in _-ray energy. The results reported by Belgya in 2006 agreed with the present one within 2–3% in the 2–8MeV region; nevertheless, the ratio showed a small oscillation versusγ-ray energy.     

Dosimetric calibration of solid state detectors with low energy β sources

A PTW Optidos plastic scintillation and a PTW natural diamond detectors were calibrated in terms of absorbed dose to water with β fields produced by ⁹⁰Sr + ⁹⁰Y and ⁸⁵Kr reference sources. Each source was characterized at the Italian National Metrological Institute - the Istituto Nazionale di Metrologia delle Radiazioni Ionizzanti of ENEA (ENEA-INMRI) - for two different series, 1 and 2, of ISO reference β-particle radiation fields. Beam flattening filters were used for the series 1 β fields to give uniform absorbed dose rates over a large area at a source-to-reference plane distance of 30 cm. The series 2 β fields were produced at source-to-reference plane distance of 10 cm, without the beam flattening filters, in order to obtain higher absorbed dose rates.The reference absorbed dose rate values were directly determined by the Italian national standard for β-particle dosimetry (a PTW extrapolation ionization chamber) for the series 1 β fields and by a calibrated transfer standard chamber, (a Capintec thin fixed-volume parallel plate ionization chamber) for the series 2 β fields. Finally the two solid state detectors were calibrated in terms of absorbed dose to water with the series 2 β field.The expanded uncertainties of the calibration coefficients obtained for the plastic scintillation dosimeter were 10% and 12% (2SD) for the ⁹⁰Sr + ⁹⁰Y and the ⁸⁵Kr sources, respectively. The expanded uncertainties obtained for the diamond dosimeter were 10% (2SD) and 16% (2SD) for the ⁹⁰Sr + ⁹⁰Y and the ⁸⁵Kr sources, respectively.The good results obtained with the ⁹⁰Sr + ⁹⁰Y and the ⁸⁵Kr β sources encourage to implement this procedure to calibrate this type of detectors at shorter distances and with other β sources of interest in brachytherapy, for example the ¹⁰⁶Ru source.     

Simulation study of personal dose equivalent for external exposure to radioactive cesium distributed in soil

The personal dose equivalent was calculated for the public (newborns; 1-, 5-, 10-, and 15-year-old children; and adults) in an environment contaminated with radioactive cesium (¹³⁴Cs and ¹³⁷Cs) distributed in a soil at specific depths of 0.0, 0.5, 2.5, 5.0, 10.0, and 50.0 g/cm², and the conversion coefficients for converting activity concentration to personal dose equivalent rate were provided for each age group. Monte Carlo calculations were performed using pediatric and adult computational phantoms incorporated into a particle and heavy ion transport code system. Compared with the effective dose and ambient dose equivalent at a height of 100 cm above the ground, the personal dose equivalent was found to provide a good estimate as a measurable quantity for the effective dose and did not exceed the ambient dose equivalent even in the environmental radiation fields, while the personal dose equivalent values increased for younger subjects. The weighted-integral method to obtain the personal dose equivalent for a volumetric source was applied to the analysis of exponential radioactive cesium distributions in the soil observed in Fukushima, and the calculation results successfully reproduced the measured data.     

Self-absorption correction for low energy gamma rays: Application to 210Pb determination in marine sediments

A series of nondestructive, low energy gamma-ray spectrometric measurements by means of intrinsic Ge detectors was carried out for the activity determinations of several naturally occurring radionuclides in marine sediments. The system was calibrated for efficiency using a radioactive sample obtained by combining standard radioactive solutions with a suitable matrix. This procedure is strictly only correct for the analysis of samples of similar composition with the same mass absorption coefficients at the investigated energies. Nevertheless, the efficiency calibration can be extended to different matrix samples if the variation in self-absorption is accurately taken into account.A method for calculating the self-absorption correction at any energy of interest is proposed and verified for the determination of ²¹⁰Pb activity at an energy of 46.5 keV. The direct gamma method and the conventional, accurate, but tedious, alpha technique via ²¹⁰Po, which can be alternatively applied to the determination of ²¹⁰Pb, agreed mostly within 8%.     

Trapping and Measuring Radioiodine (Iodine-129) in Cartridge Filters

To understand the distribution of ¹²⁹I trapped in AgS (silver-impregnated silica gel) adsorbent and to determine a calibration curve for measurement of this ¹²⁹I, cartridges containing 10 in-line (arranged in series) filter elements, each packed with a 10-mm thickness of adsorbent, were fed from 20Bq (3.3 μg) to 4.6 MBq (768mg) of ¹²⁹I at 150°C at a gas velocity of 22cm/s. The ¹²⁹I in each filter element was measured after the adsorbent had been mixed homogeneously until the counting rates at the front and back surfaces of the filter element became equal. The amount of input ¹²⁹I was allocated to each filter in proportion to the counting rates thus obtained.

The first 7 of the 10 filter elements completely confined 4.6MBq of ¹²⁹I. Therefore, the width of the adsorption zone was 7cm. Although each filter element in the cartridge could theoretically adsorb 2.92 MBq (485mg) of ¹²⁹I, the first element captured only 1.42 MBq, which was 49% of its saturation value. Its DF had dropped to a level of 2.21 for its adsorption of only 17.4% of the saturated amount. As ¹²⁹I continued to be deposited, the DF dropped to 1.45. The high gas velocity causes this phenomenon. Plots of counting rates vs. adsorption quantity provide a calibration curve covering a range of 20Bq to 2MBq of ¹²⁹I with deviation of ± 13%. This curve is expressed by

1n y = ?0.57 + 0.961n x

where y is the counting rate (counts/300s) and x the quantity of ¹²⁹I in Bq.