用CaSO_4:Dy超薄型元件对模体吸收剂量分布的测量

热释光探测器(TLD)在人体及环境辐射监测、食品辐照剂量学和治疗剂量学等的研究中已得到广泛应用。在放射生物学实验中,TLD的优点之一是可以制成各种形状和不同厚度的探测元件,以适用于动物或模型体内吸收剂量分布的测量。但是由于含较高原子序数的CaSO_4磷光体在模体中对低能散射光子的过响应,使得实验结果处理较为复杂。据文献[2]报道,对较大的~(60)Co辐照场,模型中由散射产生的低于200keV光子,使位于模型中心的CaSO_4:Dy的过响应达10％。然而若将CaSO_4材料制成极薄的TLD(其厚度远小于次级电子在组织等     

CaSO_4:Dy-Teflon元件测量~(60)Coγ射线吸收剂量分布的适用性

本文讨论了用CaSO_4:Dy-Teflon元件对狗模吸收剂量分布的测量,并与用电离室的测量结果进行比较,表明此元件能较精确地测量体模的吸收剂量分布。     

Time structure measurement of the SSRF storage ring using TRXEOL method

In order to do alignment between the timing signal and the synchrotron X-ray pulse on the sample spot in the time domain,measuring time structure of the storage ring on the sample spot inside the experimental hutch is a foundational step during the time-resolved experiments using the pulsed synchrotron X-rays with the time structure defined by the storage ring.In this work,the method of time-resolved X-ray excited optical luminescence(TRXEOL)was designed and implemented to do the measurement.It is based on the principle of time-correlated single photon counting techniques.The measurement system consists of a spectrometer with a detector of photomultiplier tube,a timing system,a set of nuclear instrument modules and a luminescent material of zinc oxide.The measurement was performed on the X-ray absorbed fine structure spectrum beamline at Shanghai Synchrotron Radiation Facility.The results show that this method can be used to measure the time structure of the storage ring with a precision of less than 1 ns.The measurement system can also be used for the time-resolved research for the optical luminescent materials.     

A Current-Mode Detector for Unfolding X-ray Energy Distribution

To turn the advantage of energy measurement in x-ray transmission diagnosis into practice, we propose a novel detector for the estimation of x-ray energy distribution. This detector consists of several segment detectors arrayed in the direction of x-ray incidence. Each segment detector measures x-rays as current. With unfolding measured currents, the x-ray energy distribution is obtained. The practical application of this detector was verified by estimating the iodine thickness in an acryl phantom.     

X-ray energy separation method using a CdTe semiconductor X-rayimaging sensor and photon counting method

A multichannel X-ray imaging sensor using a CdTe compound semiconductor radiation detector in photon counting mode was developed and tested for digital X-ray imaging and an X-ray energy separation capability. The X-ray imaging sensor was constructed of CdTe detector elements at a pitch of 0.25 mm. High band amplifiers, discriminators, and counters attached to each element formed the pulse counting circuit. Charge pulses generated by absorbed X-ray photons were directly counted and separated into two energy regions. Digitized X-ray images containing energy information were thus obtained. Using this sensor two separate X-ray images of different energy can be obtained simultaneously. A 256-channel X-ray imaging sensor was prepared and used to provide spatial resolution measurement for an X-ray charge. Low and high energy images of a hand phantom were thus obtained and both a soft tissue image and a bone image were produced using an energy subtraction method     

氧化锆检测器在微量氢同位素色谱分析中的应用研究

针对氦气与氢同位素气体热导性差异较小的问题,以氧化锆原电池为气相色谱检测器、改性γ-Al_2O_3为填充柱,在液氮温度(77K)下系统研究了氧化锆检测器测量氢同位素的影响因素,对氦气中微量氢同位素气体进行了分离测试。结果表明,氧化锆检测器的最佳工作温度约为700℃,在载气流速为60mL/min条件下,仪器测量的相对标准偏差小于1%,该方法对H2的检测下限可达15ppm,对D2的检测下限可达40ppm,样品检测的相对误差小于5%。以上结果表明,氧化锆检测器可用于氦气中微量氢同位素的分析测量。     

矿石品位仪的测量结构优化

为实现矿石品位仪的结构优化，利用蒙特卡罗（MCNP）软件，构建几何模型，模拟伽马射线在矿石品位仪系统内的输运过程。比较两种伽马放射源^60Co和^226Ra的测量效果差异，并分析了放射源与伽马探测器安装位置对测量效果的影响。结果表明，提高矿石品位仪测量效果的有效手段主要有：采用^226Ra放射源取代^60Co放射源；减小探测器与放射源距离；放射源与物料的距离调整为约30cm。     

A Semiempirical Method for Calculating Detector Efficiency as a Function of Distance

The assumption that the efficiency of a detector varies as the inverse square of the distance is valid only for a point source and a point detector in vacuum. To account for the finite size of the detector, we use the idea of an effective interaction center for that detector. The detector efficiency can then be described as varying with the inverse square of the distance between the source and the energy-dependent location of the effective interaction center. We present two simple expressions, one for the location of the effective interaction center and one for a normalization parameter. The expressions were obtained by a two-stage fitting procedure and are valid for gamma-ray energies between 60 keV and 2.615 MeV at distances of 10 cm or greater. The efficiencies so obtained agree with measurements to about 5%.     

Low dose exposure diagnosis with a transXend detector aiming for iodine-marked cancer detection

The energy resolved computed tomography (CT), which had advantage over conventional CT (twofold higher CT value for iodine contrast agent and being free from beam hardening effect), was shown practical by employing the transXend detector: it measured X-rays as electric current and gave energy distribution of incident X-rays after analysis. This article shows a new application of the transXend detector for estimating the thicknesses of acrylic, iodine, and aluminum in a phantom. For this purpose, the responses of the segment detectors in the transXend detector are changed intentionally with inserting filters. With previously obtained two-dimensional maps for acrylic–iodine and acrylic–aluminum thicknesses, which are shown by the ratios of electric currents measured by the segment detectors, the thickness of materials on the path of the X-rays are obtained by a transmission measurement.     

A quantitative assessment of heart phantom motion and its effect on myocardial perfusion SPECT images

In order to study the image characteristics of motion artifacts and to determine the relations of motion artifacts with varied motion types, and the imaging timings, frames, distances and directions during SPECT acquisition, a myocardial phantom filled with pertechnetate solution was used to simulate the patient motion. In nonreturning pattern, the simulation motion was timed at the 0°, -45° and -90° positions during the rotation of the detector over a 180° arc from ±45° right anterior oblique to -135° left posterior oblique. Simulation motion was performed by moving the phantom ±5mm, ±10mm and ±20mm along X- (from left to right), Y- (from head to caudal) and Z-axis (from back to ventral) respectively. In returning pattern the acquired 30 projections were divided into three equal parts. The simulation motion was timed at the middle 1-7 projections of each part and performed by moving the phantom ±5, ±10,±15, ±20, ±25, ±30 and ±50 mm along X-, Y- and Z-axis respectively. Each image was co     

贝叶斯理论在脉冲裂变中子能谱诊断中的应用

本文建立了以贝叶斯理论为基础的脉冲裂变中子能谱的数值迭代计算方法,解决了脉冲裂变中子能谱测量的技术难题。对脉冲裂变中子空间输运、物质衰减、探测器灵敏度等进行了分析,将脉冲裂变中子能谱在空间传输中的飞行展宽时间谱理解为出壳时间谱在不同测点的概率分布函数,脉冲中子在不同测点的信号强度分布是出壳时间谱和脉冲中子能谱飞行展宽时间谱的卷积信号,将物质衰减、探测器灵敏度响应等转换环节对中子能谱的影响因子进行了分别处理,消除了通道物质对中子能谱衰减和探测器非线性灵敏度等因素对脉冲裂变中子能谱解谱的影响。研究结果表明,对距辐射源5 m和10 m处的中子波形进行数值处理,均能获得理想的脉冲裂变中子能谱,当考虑传输系统响应函数对中子波形影响时,仍能获得较理想的中子能谱。     

研究微剂量学的Q型计数器

探讨了在纳米量级研究重离子微量剂量学的重要性，在此基础上建立了一套研究重离子微剂量学的实验装置。它包括探测器，可远距离遥控的高精度三维微动装置，足够大的靶室系统，可对工作气体的气压进行测量和调节的气压稳定系统以及进行电离分布研究的电子学系统。     

γ射线测距中散射光子影响因素的蒙特卡罗模拟

基于散射光子的γ射线测距技术,具有测距精度高、响应速度快、可靠性高、体积小、重量轻等特点,适用于在苛刻空间环境中实现近距离高精度的高度测量。本文采用蒙特卡罗程序MCNP建立模型,模拟不同条件下散射光子的能量、强度的变化规律,分析了探测距离、源 探距离、γ射线能量、靶目标厚度以及靶目标材料的变化对反散射峰光子能量与强度的影响,得出以下结论：反散射峰光子能量与靶目标厚度（>7 cm）、靶目标材料无关,与γ射线能量、源 探距离正相关,与探测距离负相关;反散射峰光子强度与靶目标厚度（>7 cm）无关,与探测距离正相关,与γ射线能量、源 探距离、靶目标材料负相关。对于不同靶目标材料,模拟计算的反散射峰光子能量分布区间与理论计算结果一致,证实本文γ射线散射光子测距技术的仿真方法可行、结果可信。     

肺部计数器虚拟校准结果的影响因素

内照射活体测量中,肺部计数器通常忽略肺以外其他器官中沉积的放射性核素对探测器计数的贡献,且校准使用的参考体模和被监测人之间会有身体形态的差异。本文利用中国成年男性体模库,采用蒙特卡罗程序模拟计算了~(65)Zn和~(60)Co核素的器官源探测效率,并计算了总探测效率,研究了这两个因素对虚拟校准的影响。结果表明,对于类似65Zn的核素不能忽略肺部以外其他器官源的计数贡献;同一身高下,肺部计数器对~(65)Zn和~(60)Co核素的总探测效率随体重增加而降低,且对于65Zn核素的降低比例会随摄入时间而变化;对于同一体模的总探测效率会随时间而降低。由此证明,核素生物动力学分布和体模形态的差异对肺部计数器总探测效率均有较大影响,且对不同核素影响会有不同。     

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.     

The measurement of the absolute intensity of neutron sources by a comparison with the reaction T(d,n)He4

A method for the measurement of the absolute intensity of neutron sources by a comparison with the neutron intensity from the reaction T(d, n)He⁴ is described. For the comparison of the intensities a detector was used which has an almost constant sensititity for a wide range of neutron energies. The detector consisted of a graphite prism in which, at a definite distance from the source (“constant”-sensitivity distance), the density of thermal neutrons was measured. The sensitivity of such a detector is constant, to an accuracy of 1–2 %, in the interval of neutron energies 0.1–8 Mev and is 13% lower for neutrons of energy 14 Mev. In 1953 this method was used for the measurement of the absolute intensity of a Ra-α-Be source with an accuracy of 4%.     

高纯锗探测器探测效率研究

利用系列标准γ射线源对高纯锗探测器的探测效率进行了各种测量,与蒙特卡罗计算程序相结合,对于高纯锗探测效率进行了分析和讨论.计算效率与测量效率在4%以内吻合.在一定探测距离条件下面源与点源的探测效率在1%以内吻合,而且面源的自吸收可以用平行束在材料中的自吸收来计算;当面源靠近探测器时,由于γ射线的倾斜入射,这种方法就不适用了,需要用蒙特卡罗方法进行自吸收较正.     

Correction Factor for Potassium-40 Whole-body Counting

Correction factors, correlation between ⁴⁰ K whole-body counting efficiencies and a simple physical parameter, were determined using Monte Carlo simulation. The surface area of a subject was adopted as the correction factor parameter for practical routine use in the interpretation of response functions from the subject, and from the relationship between the surface area and counting efficiencies of a whole-body counter a correction equation was derived.

To testify the feasibility of the correction factor, the ⁴⁰K contents in the total body of Japanese male adults were measured with a whole-body counter, and the ⁴⁰K contents corrected by using the correction equation were compared with those estimated with a bioelectrical impedance instrument. The quantitative agreement of the ⁴⁰K contents corrected by whole-body counting with those estimated by means of the bioelectrical impedance instrument is fairly good.

The response function and counting efficiency of the whole-body counter to a ⁴⁰K phantom were obtained by calculation and actual measurement. It was found that calculation by the EGS4 code agrees very well with the measurement.     

可控中子源密度测井仪的密度响应特性与算法研究

在可控中子源密度测井中，脉冲中子源的中子产额存在波动，采用探测器绝对计数的密度算法受地层环境、测量条件的影响较大，因此会导致密度算法的精度较差。为提高密度测量的稳定性和精确性，本文针对可控中子源一体化测井仪的研发需要，建立了适合所研发仪器的密度算法：首先，结合蒙特卡罗数值模拟软件MCNP对新型一体化测井仪及地层进行了建模；然后，利用所建模型，模拟了在不同岩性、孔隙度条件下可控中子源发射的快中子与地层物质的相互作用过程，并通过记录γ探测器的近、远非弹性散射γ计数和俘获γ计数，中子探测器的近热中子及近超热中子计数信息，获得了一体化测井仪探测器计数与地层密度之间的响应关系，并对影响密度算法的主要因素进行了分析；最后，在密度响应特性分析的基础上，提出了使用近超热中子与近热中子计数比、近远非弹γ计数比来提高稳定性和精确性的可控中子源密度测井新算法。采用新密度算法对所建模型进行计算，结果表明，砂岩、灰岩、白云岩3种岩性下计算的密度与真密度非常接近，其相对误差小于6%。与哈里伯顿和斯伦贝谢算法的计算结果相比，本文方法显示了更好的效果：公式参数少、没有探测器的绝对计数、精确度高。     

用样条函数拟配Ge(Li)γ谱仪效率曲线方法

本文采用三阶样条函数作为Ge(Li)γ谱仪效率曲线模型,使用并改进了逐步回归算法,利用AIC检验等手段对模型加以优化,解决了分点数量、最佳分点位置及分点处的连续性等问题。所得模型具有参数少、精度高等优点。 利用本方法对本实验室所用185cm~3同轴Ge(Li)探测器进行效率刻度,在59～1408keV范围内,所得模型都只含3个参数,精度为2.5％左右。利用刻度好的系统标定~(152)Eu的发射率,与国际比对值相比,偏差≤3％。