基于改进粒子滤波的未知放射源定位方法

为应用自主移动机器人搜寻未知放射性物体,本文基于递推贝叶斯估计模型提出了一种改进粒子滤波的放射源定位方法。首先,建立初始粒子集,并根据观测值对粒子权值进行更新和归一化;其次,在重采样过程中引入自优化的重采样方法来增加粒子多样性;最后,对满足收敛条件的粒子进行加权求和估计出放射源位置与活度参数。仿真实验表明该方法可行有效：无屏蔽环境下具有较高的定位精度;有屏蔽环境下也能找到放射源的大致位置,为放射源的最终定位提供参考。     

Development of a dose-adjustable α-particle irradiation facility for radiobiological studies

Bystander effects induced by low-dose or low dose-rate radiation have put a great challenge to the traditional model for radiation protection. In order to get a better assessment of the adverse effects of radiation, especially the low-dose radiation risk in environment, a radioactive irradiation facility, by which the dose and dose-rate to the biological targets can be controlled by rotating the sample bracket and changing the space between the radioactive source and the targets, was developed. The energy of our α-radioactive source (241Am) is measured averagely 3.5MeV at the position of the irradiated sample. The dose rate was measured by using a silicon surface barrier detector and a CR39 particle track detector. A dose rate ranging from 0.045 cGy/s to 1.07 cGy/s can be obtained by changing the space length from the radioactive source to the sample dish.     

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。     

粒子望远镜对运动放射源绝对探测效率的研究

文章描述了在延迟粒子谱学研究中所常用的氦喷咀系统的粒子望远镜，并对运动的放射源的绝对探测效率进行计算。考虑具有一定分布的放射性面源，计算光栏和放射源偏离中心位置对探测效率的影响。将计算过程编制成计算机程序以处理实验数据。     

放射源壁厚被动识别的可行性分析

放射源壁厚是强γ辐射环境γ定量测量和军控核查中所关注的一个重要参数。本工作根据γ全能谱中同一放射核素的不同能量γ射线出射强度比与源壁厚的关联性研究了源壁厚的被动γ测量方法。实验测量的源壁厚与真值基本吻合,表明通过被动γ法测量源壁厚是可行的。     

放射性气溶胶粒径分布测量软件研究

为基于筛网扩散组的放射性气溶胶粒径分布测量系统研制了一套测量分析软件,软件的运行环境为基于ARM的嵌入式硬件系统和linux嵌入式操作系统。软件使用开源QT套件开发。系统功能包括测量过程控制,筛网扩散组透过率计算,粒径分布的测量,测量数据分析计算的EM算法和Twomey算法,粒径分布的显示,系统通讯等功能。     

蒙特卡罗方法模拟放射源位置对井型NaI(Tl)晶体探测效率的影响

利用Geant4数值计算程序,对放射源137Cs和60Co发射的单能γ射线(0.662 MeV和1.331MeV)经过井型NaI(Tl)晶体探测器后的能谱进行了蒙特卡罗模拟,并通过改变放射源在井型NaI(Tl)晶体中的位置对探测效率的影响做了进一步的研究。计算结果表明:对比常用的圆柱形NaI(Tl)闪烁探测器,由于井型NaI(Tl)晶体对放射源所张立体角很大,所以其对γ射线的源峰探测效率更高,并随着放射源在井内高度的增加而逐渐减小;在固定了放射源在晶体井下深度的情况下,放射源位置在水平面内的变化对源峰探测效率的影响并不大。     

基于三晶体耦合γ射线方向探测器的放射源定位

为了快速定位并寻回丢失的放射源,设计了一种由NaI、CsI、锗酸铋(Bi4Ge3O12,BGO)三种晶体与铅耦合组成的γ射线方向探测器,并采用基于蒙特卡罗方法的通用软件包MCNP(Monte Carlo N Particle Transport Code)研究了铅晶比例、射线能量、剂量率等因素对探测器角度分辨率的影响。结果表明,对于137Cs源,在空气吸收剂量率≥0.331μGy·h~(-1)处,定位角度偏差≤0.99°;对于60Co源,在空气吸收剂量率0.586μGy·h~(-1)处,测量的平均角度偏差为0.46°;对于水平距离7 m、高度4 m的3.7×107Bq 137Cs源,相对定位偏差约为5%。     

D-T中子源束斑尺寸测量技术及应用

D-T中子发生器作为高能中子源,已用于特种核材料的有源探测技术中,利用时间符合法可实现被测物体的多模式成像,而中子源束斑尺寸是影响成像位置分辨的一个重要的因素。因此,结合D-T反应的特点和实际应用环境,开发了n-α关联符合测量确定中子源束斑尺寸的方法。利用该方法对小型移动中子发生器的束斑尺寸进行了测量,获得的束斑尺寸为(2.8±0.9) mm,与用CCD相机直接观测得到的约3 mm的测量结果一致,证明了该方法测量束斑尺寸的可行性。该方法也可用于辅助D-T中子源调束和关联粒子成像实验过程中的束斑监测。     

Beam Spot Size Measurement Technology and Application for D-T Neutron Source

As a high-energy neutron source, the D-T neutron generator has been used in the active detection technology of special nuclear materials. The time coincidence method can be used to achieve multi-mode imaging of the measured object, and the beam spot size of the neutron source is a very important factor that affects the imaging position resolution. Therefore, combined with the characteristics of D-T reaction and practical application environment, a method for n-α correlation coincidence measurement to determine the beam spot size of neutron source was developed. This method was used to measure the beam spot size of a small mobile neutron generator. The beam spot size obtained is （2.8±0.9） mm, which is consistent with the measurement result of about 3 mm obtained by direct observation with CCD camera, which proves that this method is feasible. This method can also be used to assist D-T neutron source beam tuning and beam spot size monitoring in associated particle imaging experiments.     

125Ⅰ放射性粒子源水中吸收剂量的修正方法探讨

放射性粒子植入技术是利用粒子持续释放的射线摧毁肿瘤的治疗手段.临床治疗时需要种植粒子,确保剂量分布均匀合理,本研究介绍了一种125Ⅰ放射性粒子源在水中的吸收剂量的修正方法.为确保粒子在人体内的植入位置和辐射剂量提供指导.结果显示,在距离125Ⅰ放射性粒子源表面5mm处,经修正的数值约为原值的1.3倍,其影响程度随着距离的增大而逐渐变小.结果表明,125Ⅰ粒子源在水中的吸收剂量测量值有必要进一步修正.     

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。     

The design and calibration of a phantom for depth profiling measurements of entrained radioactivity in silica-based media

The development of a phantom which replicates the effect of concrete on radioactivity entrained within it is described. The phantom was designed as a basis on which methods can be developed to measure the depth of radioactive contamination in the concrete of defunct nuclear facilities. In particular, this apparatus has been used to validate a differential attenuation method for the profiling of radioactive contamination at depth. Entrained radioactive contamination is a significant issue in defunct nuclear facilities where in situ, non-destructive assay of radioactive waste arisings is a routine requirement.The phantom comprises a polymethylmethacrylate structure filled with high-purity silica-sand which, for the purposes of the application, is an effective analogue of fully-hydrated concrete paste. A void was created within the silica sand which incorporates a sliding mechanism for the insertion of a radioactive source to a required depth. The sealed source represents the entrained radioactivity in the phantom but is also specifiable, removable and poses no long-term contamination risk beyond the expected life of the apparatus. The remainder of the void either side of the source is filled with silica-sand to complete the homogeneity of the phantom. The void was situated near the front of the phantom constructed at a 5.14° angle with respect to the front scanning surface; thus the apparent depth within the silica-sand can be varied by changing the position of the source along the phantom's void.The steps taken to develop the concrete phantom are described. The design has been validated with a set of radiation transport simulations affording comparison with an exemplar of the concrete found used in nuclear facilities. Some initial results from measurements taken with the phantom and a caesium-137 γ-radiation source in combination with a sodium iodide radiation detector are provided. These measurements are used to validate the differential attenuation method and compared with data from previous measurement attempts with concrete slices.     

基于Cerenkov效应水下放射源搜寻技术的可行性分析研究

本文采用Geant4对水下放射源致Cerenkov光及Cerenkov光在水中的输运过程进行计算研究,获得Cerenkov光强及光子数在水平面上的分布规律,进而对该技术手段进行了理论验证和可行性分析。研究结果表明:当放射源出射粒子能量满足产生Cerenkov光的条件时,其在水面形成的Cerenkov光斑及Cerenkov光子数在水面的分布具有规律性,可以此来确定放射源的位置和深度。本工作为基于Cerenkov效应水下放射源搜寻技术的发展提供了理论依据和科学基础。     

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。     

简化源项计算方法

利用程序包STCP估算核电厂在发生严重事故情况下释放到环境的放射性源项需要耗费大量计算机时间和费用。所以,对所有感兴趣的事故情景完成源项程序包的计算实际上是不可能的。为此,发展了一个简化源项计算方法。它的基本思想如下:首先利用STCP计算几个选择的序列,然后根据放射性释放和事故进程的特点处理和分析由STCP计算得到的结果,得出一些特定参数,其它事故序列的源项能够通过这些参数的重新组合得到。     

锰浴法测量中子源发射率中各修正因子的蒙特卡罗计算

在采用锰浴法对放射性同位素中子源的发射率进行测量时,MnSO₄溶液中⁵⁵Mn仅俘获部分源中子,故需考虑对未被⁵⁵Mn俘获部分的修正。用蒙特卡罗粒子输运程序MCNP对中子源强标准装置的锰浴系统进行模拟计算,对实验测量结果进行修正,并通过由国际计量局（BIPM）组织的中子源强度国际比对,验证了计算所建立模型的可靠性。利用MCNP程序的微扰计算功能,通过考虑MnSO₄溶液的密度、源及其承托物材料的密度、源的位置、锰浴半径以及反应截面的改变对计算结果的影响,对模拟计算结果的不确定度进行了详细评定,提供了一种蒙特卡罗模拟计算结果不确定度的评定方法。     

放射性核素电离空气电子离子对产生率计算

α衰变核素和β衰变核素发射的射线具有电离空气能力而被广泛应用于工业生产中。为研究α或β衰变核素对空气电离能力的大小,本研究采用蒙特卡洛方法模拟理想放射源发出带电粒子在空气中的能量沉积,并结合空气电离理论,计算放射源表面不同距离处电子离子对产生率。利用此计算方法,研究放射源形状、粒子能量、活度和粒子能量分布对电子离子对产生率的影响。结果表明,放射源表面空气中电子离子对产生率的大小主要受放射源活度的影响,而粒子能量及能谱分布等主要影响电离空气范围及电子离子对产生率衰减速率; 3.7×10⁶ Bq/cm²的α放射源最大电子离子对产生率可达10¹¹~10¹² cm^-3•s^-1量级, 3.7×10⁶ Bq/cm²的β放射源最大电子离子对产生率可达10⁹~10¹⁰ cm^-3•s^-1量级。研究结果可提供数据支持,为新的放射性同位素应用技术开发提供理论指导。     

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.     

基于光滑粒子与有限元耦合算法的放射性废液运输容器跌落分析

基于光滑粒子和有限元耦合算法,利用显式动力学分析软件LS-DYNA,对装载放射性废液的车载式废树脂接收装置在三种不同跌落方式下的跌落冲击过程进行了数值分析。以装置水平跌落为典型算例,对其在跌落过程中所受的动态激励、装置的压力变化和装置的应力状态进行了分析。结果表明,光滑粒子和有限元耦合算法对于解决装载放射性废液的运输容器在跌落冲击过程中流固耦合问题是有效的。同时,基于有限元分析结果,提出了一种按照RCC-M《压水堆核岛机械设备设计和建造规则》等规范对放射性物质运输容器跌落冲击过程进行应力强度评定的方法,并依据该方法对装置的结构强度进行了评定,结果显示装置在三种不同跌落方式下的应力强度均满足要求。