10 MeV同轴腔电子加速器辐射屏蔽设计

中国科学院近代物理研究所自主研制了一台同轴腔电子加速器,能产生10 MeV,10 mA的辐照电子束,建成后有望成为我国首台国产化的花瓣形电子辐照加速器。为保证该装置运行时的辐射安全,为今后同类型装置的辐射屏蔽设计提供参考,对该加速器开展了辐射屏蔽研究。首先结合装置的使用情况给出了一种地上为主机室地下为辐照室的半地下机房结构,然后采用蒙卡程序FLUKA计算了相关墙体的厚度。在蒙卡计算中,基于同轴腔加速器的束流损失特点,建立了适用于该类型装置的蒙卡源项输入模型,充分考虑了决定辐射场的主要束损点,同时设置相对简单。结果表明:在设定的屏蔽外剂量率目标下,以普通混凝土作为屏蔽材料,主机室的侧墙、顶板和辐照室顶板的厚度分别需要160～220,110～150,150 cm。     

一种高重频废束桶束窗的设计及热结构分析

深圳中能高重频X射线自由电子激光（S3FEL）将建设成为全球唯一软X射线波段的高重频自由电子激光。废束桶是S3FEL装置的重要设备,在系统调束中发挥着重要作用。废束桶束窗是废束桶的重要组成部件,用于隔离和保护加速器超高真空环境。本文对几种常用的废束桶束窗材料进行了对比分析,最终选择铍作为束窗的材料,并依此设计了一种带有水冷结构的束窗。通过蒙特卡罗方法计算得到不同厚度束窗的沉积功率,采用有限元分析方法对不同厚度的束窗进行热结构计算与分析,得到厚度为1.6 mm的水冷铍窗效果最佳,其最大温度为121.6℃,低真空为1 Pa时的最大应力与中心变形分别为198.7 MPa和0.000 82 mm,低真空为101 325 Pa时的最大应力与中心变形分别为204.2 MPa和0.097 mm,结果均满足使用要求。此研究为S3FEL的废束桶束窗设计提供了重要的理论依据。     

束流在270°偏转磁铁系统输运过程中的损失计算

为计算医用加速器中束流经过270°偏转磁铁系统电子损失所造成的辐射剂量问题,将束流传输相应的计算公式和蒙特卡罗抽样方法相结合,在一阶近似条件下计算了电子在偏转系统中的输运过程,分析了不同初始条件对电子输运和电子损失的影响;模拟结果表明能散是产生电子损失的主要因素之一.计算得到了损失电子所处位置、能量和飞行方向等信息,把计算得到的信息作为蒙特卡罗程序的输入源,进一步计算出束流损失所产生的辐射剂量分布,从而能更完善地设计医用加速器照射头的屏蔽.文中给出在电子束初始半径为1mm、散角为5mrad、能散为10%条件下电子损失率为13.5%,损失电子主要是向加速器照射头部上方辐射出去.     

束流在270°偏转磁铁系统输运过程中的损失计算

为计算医用加速器中束流经过270°偏转磁铁系统电子损失所造成的辐射剂量问题, 将束流传输相应的计算公式和蒙特卡罗抽样方法相结合, 在一阶近似条件下计算了电子在偏转系统中的输运过程, 分析了不同初始条件对电子输运和电子损失的影响；模拟结果表明能散是产生电子损失的主要因素之一. 计算得到了损失电子所处位置、能量和飞行方向等信息, 把计算得到的信息作为蒙特卡罗程序的输入源, 进一步计算出束流损失所产生的辐射剂量分布, 从而能更完善地设计医用加速器照射头的屏蔽. 文中给出在电子束初始半径为1mm、散角为5mrad、能散为10%条件下电子损失率为13.5%, 损失电子主要是向加速器照射头部上方辐射出去.     

NaI闪烁探测器测量感生放射性及其蒙特卡罗模拟

描述了如何使用蒙特卡罗方法评估产生在加速器屏蔽混凝土中的感生放射性. 使用EGS4程序模拟了NaI闪烁探测器测量屏蔽混凝土块表面剂量率时, 对于半径和厚度的响应. 结果发现,在屏蔽混凝土块半径和厚度分别达到40cm和30cm时, 表面剂量率达到饱和. 研究了东京大学SF回旋加速器北墙位置8和位置9的表面剂量率, 并和使用NaI闪烁探测器的测量结果进行了对比, 发现模拟和实验结果符合很好. 并且, 获得了表面剂量和表面感生放射性之间的转换系数, 对于⁶⁰Co转换系数为0.90(Bq·g^－1)·(μSv·h^－1)^－1, 对于¹⁵²Eu转换系数为1.26(Bq·g^－1)·(μSv·h^－1)^－1. 这样, 就可以通过NaI闪烁探测器表面剂量的测量结果简单评估加速器设备屏蔽混凝土中的感生放射性.     

低能粒子加速器的辐射场

前言加速器的辐射场主要来源于加速器运行期间产生的次级辐射。不同类型的加速器产生的次级辐射的种类和强度不尽相同。加速器屏蔽设计主要依据其可能产生的最大次级辎射强度。因此屏蔽厚度的确定必须综合考虑加速粒子的种类、能量、束流强度以及靶材料的性质等各种因素。同时还应考虑相邻区域的类型和人口密度,以便使周围群体的集体剂量当量保持在可以合理做到的尽可能低的水平,并保证个人所接受的剂量当量不得超过相应的剂量当量限值。     

CT靶物质的辐射特性研究

采用Monte Carlo模拟程序MCNP4B对电子-光子在CT靶物质中的耦合输运进行了模拟. 对几种靶的光子效率和X射线前向性随靶厚度变化进行了计算和分析. 模拟计算结果表明, 与电子加速器中常用的Au, W等高Z靶相比, Cu靶具有特殊的辐射物理性质: 1) 光子效率对Cu靶厚度不敏感. 通常, 对于高Z靶, 光子效率在靶厚度为某特定值时达到最高值, 然后随靶厚度增加而迅速减小; 而对于Cu靶, 光子效率在达到最大值后, 靶厚度再增加时, 光子效率仅略有减小, 且变化趋于平缓. 2) 电子束轰击Cu靶时, 虽然光子效率较低, 但是角分布具有很好的前向性, 且前向剂量率可与Au靶、W靶相当. 实验结果表明, 用能量为20MeV的电子轰击Cu靶时, 前向0°附近的X射线剂量率达到并超过了用W靶时的结果, 而且剂量率角分布比W靶的前向性好.     

回旋加速器束测探头感生放射性实验研究

基于束流沉积法测量回旋加速器内部束流参数将在束测探头上产生感生放射性污染,从而对加速器调束工作人员带来不必要的辐射危害。采用AGM-6型监测仪对探头感生放射性进行在线测量,通过测量不同半径处探头受辐射后的空气比释动能率,间接反映探头感生放射性的强弱和危害。研究结果表明,在束流调试实验中,应尽量降低馈入高频的占空比;探头测量后冷却2~3 h取出,则不需要考虑测量探头辐照后的残留感生放射性的危害。     

电子束和β射线两用外推电离室

电子束辐照在辐射加工、新材料研制、放射治疗和模拟空间辐射环境的各种科学实验中应用日益广泛.实践表明,在上述应用中,被照物体吸收剂量是决定成功与失败的关键.因此,近年来准确测定电子束在各种材料中的剂量分布已成为迫切需要解决的问题. 由于电子束和β射线在物质中的迁移和能量沉积行为十分复杂,所以至今也难以从理论上给出准确的吸收剂量率随深度变化的统一解析式.目前,各种解析、模拟和半经验的计算电子剂量分布的方法已经产生,但具体给出准确的电子剂量分布仍然要靠实验测定.一般来讲,对不同加速器,即使具有相同的标称能量(加速器…     

100 MeV质子束流品质诊断及剂量测量准确性评估方法研究

质子辐射生物学效应是太空放射生物学和质子束放疗研究的重要基础，可为空间环境下人员的危险性评估以及质子治疗优化设计提供科学依据。依托加速器建立相应的生物样本辐照技术是开展此类研究的前提条件。中国原子能科学研究院最近建立的100 MeV强流质子回旋加速器提供的中能质子束流为目前国内能量最高，特别适合用于太空放射生物学和质子治疗相关研究。本研究中，利用在束和离线等多种手段建立了中能质子束流诊断和剂量测量方法，对加速器引出的100 MeV质子照射野大小、均匀性等束流品质以及剂量测量系统准确性进行了分析和评估。结果表明，对光子剂量响应好的LiF(Mg, Ti)热释光探测器，对90 MeV质子同样具有良好的剂量响应关系，可作为中能质子剂量准确性评估的手段之一。在5.0 cm×5.0 cm照射野范围内，加速器引出的100 MeV质子束流的均匀性好于90%，在线剂量测量系统准确性好于93%，束流品质和剂量测量条件基本满足辐射生物学的要求，可为质子辐射生物学效应研究的开展提供可靠保障。     

The use of recombination chambers at radiation therapy facilities

The paper presents an overview of the applications of recombination chambers for dosimetric measurements at radiotherapy facilities. The chambers were used at electron, proton and heavy ion accelerators, in the beam and in the vicinity of the accelerators at very different dose rates. The examples of measurements discussed in the paper include: the determination of the absorbed dose and radiation quality parameters of a 170 MeV proton beam and BNCT (boron neutron capture therapy) beam, neutron dose measurements at a phantom surface outside the beam of a 15 MV electron medical accelerator, determination of ambient dose equivalent, H1 (10) outside the irradiated phantom in the proton therapy treatment room at JINR (Dubna, Russia), and at working places outside the shielding of the heavy ion therapy facility at GSI (Darmstadt, Germany).     

Study on the radiation problem caused by electron beam loss in accelerator tubes

The beam dynamic code PARMELA was used to simulate the transportation process of accelerating electrons in S-band SW linacs with different energies of 2.5, 6 and 20 MeV. The results indicated that in the ideal condition, the percentage of electron beam loss was 50% in accelerator tubes. Also we calculated the spectrum, the location and angular distribution of the lost electrons. Calculation performed by Monte Carlo code MCNP demonstrated that the radiation distribution of lost electrons was nearly uniform along the tube axis, the angular distributions of the radiation dose rates of the three tubes were similar, and the highest leaking dose was at the angle of 160° with respect to the axis. The lower the energy of the accelerator, the higher the radiation relative leakage. For the 2.5 MeV accelerator, the maximum dose rate reached 5% of the main dose and the one on the head of the electron gun was 1%, both of which did not meet the eligible protection requirement for accelerators. We adopted different shielding designs for different accelerators. The simulated result showed that the shielded radiation leaking dose rates fulfilled the requirement.     

400 MeV/u碳离子打靶的屏蔽参数计算

为了给医用重离子加速器提供一种专用的快速计算屏蔽厚度或对蒙特卡罗模拟结果进行验证的方法。采用FLUKA程序完成了400 MeV/u碳离子打不同靶的屏蔽参数计算。首先研究了打厚靶(铁、水)产生的次级辐射场的角度分布及主要成分;接着给出了不同角度范围下周围剂量当量在屏蔽体中的衰减曲线,通过拟合数据进一步得到不同角度范围下的辐射源项值H₀和衰减长度λ₀;最后结合莆田市医用重离子加速器治疗室的屏蔽设计,介绍了此套屏蔽参数的使用方法,通过与蒙特卡罗模拟结果的对比,证明了这套屏蔽参数的可靠性。该参数可为同类医用重离子加速器的屏蔽设计提供可靠的参考数据。     

正电子发射成像回旋加速器屏蔽材料防护性能

计算了11 MeV 正电子发射成像回旋加速器18O(p, n)18F反应的双微分截面数据,并采用蒙特卡罗模拟计算方法,分析了单一材料及复合结构对特定辐射源的防护性能。采用单一材料,质量分数为73.8%的重混凝土的防护效果最佳,经过90 cm厚屏蔽层的衰减,距离辐射源正前方1 m处的总剂量降低约5个量级;复合结构采用多层结构,材料选用铁及硼酸溶液,同样厚度即可达到与重混凝土相同的防护效果,密度可降低至少20%。     

应用MORSE程序计算中子的天空反散射

用中子源模拟粒子加速器，以MORSE程序分析计算由于天空反散射引起的中子剂量当量的变化规律，揭示了天空反散射的实质，计算结果可供加速器或核设施环境评价和防护设计使用．计算模型采用将中子源置于空心圆柱体中，圆柱体分为有顶盖屏蔽和无顶盖屏蔽两种情况．中子源能量分别为2.38MeV、14Mev和巨共振中子．中子源为各向同性．此外，还分析计算了不同的发射立体角和不同散射介质的影响．     

Dose estimation and shielding calculation for X-ray hazard at high intensity laser facilities

An ionizing radiation hazard produced from the interaction between high intensity lasers and solid targets has been observed. Laser-plasma interactions create "hot" electrons, which generate bremsstrahlung X-rays when they interact with ions in the target. However, up to now only limited studies have been conducted on this laser-induced radiological protection issue. In this paper, the physical process and characteristics of the interaction between high intensity lasers and solid targets are analyzed. The parameters of the radiation sources are discussed, including the energy conversion efficiency from laser to hot electrons, hot electron energy spectrum and electron temperature, and the bremsstrahlung X-ray energy spectrum produced by hot electrons. Based on this information, the X-ray dose generated with high-Z targets for laser intensities between 10¹⁴ and 10²⁰ W/cm² is estimated. The shielding effects of common shielding items such as the glass view port, aluminum chamber wall and concrete wall are also studied using the FLUKA Monte Carlo code. This study provides a reference for the dose estimation and the shielding design of high intensity laser facilities.     

The simulated workplace field with a high-energy neutron component produced by irradiating a Fe-target with 200 MeV/u 12C-ions

Recent developments in accelerator physics have led to new challenges for radiation protection dosimetry. Doses have to be determined for workplace fields which are characterized by high-energy radiation, a dominant contribution from neutrons, high intensities and pulsed time structure This may present problems for active measuring devices. As is well known, the ambient dose equivalent is often underestimated by area monitors operating in high-energy neutron fields behind shielding. Therefore, it is desirable to calibrate survey monitors in a characterized neutron field with the type of spectral fluence distribution that is expected behind shielding, i.e. where the main dose from neutrons arises from two peaks with mean energies of about 1 MeV and 100 MeV, respectively. Such a neutron fluence distribution is produced by the irradiation of a Fe-target with 200 MeV/u ¹²C-ions. Measurements with the extended range Bonner sphere spectrometer NEMUS of PTB were performed at two positions inside the experimental area Cave A of the heavy-ion synchrotron SIS at GSI. The measured neutron spectra show different fluence contributions for the two peaks at the two positions. The results were compared to Monte Carlo Simulations with MCNPX and FLUKA.     

基于蒙特卡罗方法的XHA600D医用电子直线加速器的入射电子束参数研究

使用蒙特卡罗方法研究入射电子束参数对XHA600D医用电子直线加速器产生的剂量分布的影响,并确定优化的入射电子束参数。根据厂商提供的XHA600D加速器治疗头的几何、材料参数,使用蒙特卡罗程序EGSnrc对不同的入射电子束参数进行模拟并记录其在水模体中产生的剂量分布,将模拟结果与测量结果进行比较。模拟的入射电子束参数包括平均能量、径向强度分布、角度展宽和能量展宽;实验测量数据包括4 cm×4 cm、10 cm×10 cm、30 cm×30 cm射野条件下的百分深度剂量与离轴剂量。结果表明当入射电子束的平均能量为6 MeV、径向强度的半高宽(Full Width at Half Maximum, FWHM)为0.25 cm、角度展宽为0.15°时,模拟结果和测量结果吻合非常好。这些参数可以作为建立适用于XHA600D加速器的TPS(Treatment Planning System)剂量计算模型的基础参数。     

100 MeV强流质子回旋加速器束流调试靶系统

中国原子能科学研究院正在建造一台100 MeV,200 A的强流质子回旋加速器,需要使用束流调试靶来调试加速器,为此设计了一套束流功率为20 kW的质子束调试系统。对该系统的束流输运线、靶材料的选取、靶结构、水冷计算、屏蔽结构等作了介绍。给出了整条束流输运线的匹配计算结果;通过对质子打靶后的中子产额、角通量、靶的活化等方面的比较,最终选用铝作为靶材料;根据加速器引出束流能量和功率,设计了分层式靶结构,同时对靶进行了水冷计算;打靶产生的出射粒子平均能量较高,导致产生的辐射剂量很大,考虑到对环境与工作人员的影响及费用,需要对其进行局部屏蔽,给出了屏蔽计算结果及屏蔽结构的设计。     

Dosimetric measurements and Monte Carlo simulation for achieving uniform surface dose in pulsed electron beam irradiation facility

A prototype pulsed electron beam irradiation facility for radiation processing of food and medical products is being commissioned at our centre in Indore, India. Analysis of surface dose and uniformity for a pulsed beam facility is of crucial importance because it is influenced by various operating parameters such as beam current, pulse repetition rate (PRR), scanning current profile and frequency, scanning width and product conveying speed. A large number of experiments are required to determine the harmonized setting of these operating parameters for achieving uniform dose. Since there is no readily available tool to set these parameters, use of Monte Carlo methods and computational tools can prove to be the most viable and time saving technique to support the assessment of the dose distribution. In the present study, Monte Carlo code, MCNP, is used to simulate the transport of 10 MeV electron beam through various mediums coming into the beam path and generate an equivalent dose profile in a polystyrene phantom for stationary state. These results have been verified with experimentally measured dose profile, showing that results are in good agreement within 4%. The Monte Carlo simulation further has been used to optimize the overlapping between the successive pulses of a scan to achieve ±5% dose uniformity along the scanning direction. A mathematical model, which uses the stationary state data, is developed to include the effect of conveyor speed. The algorithm of the model is discussed and the results are compared with the experimentally measured values, which show that the agreement is better than 15%. Finally, harmonized setting for operating parameters of the accelerator are derived to deliver uniform surface dose in the range of 1–13 kGy/pass.