医用加速器X-射线射野剂量分布的蒙特卡罗模拟与实验测量

用电离室测量及蒙特卡罗方法计算水模体中瓦里安6 MV X-射线射野的百分深度剂量和射野离轴比,对测量和计算结果进行比较和分析。结果表明:10 cm×10 cm射野百分深度剂量在0-20 cm深度范围内,按2 mm/2%标准,?≤1的通过率为96.47%,按3 mm/3%标准,?≤1的通过率为99.23%;射野离轴比按2 mm/2%标准,?≤1的通过率为97.56%,按3 mm/3%标准,?≤1的通过率为99.42%;10 cm×10 cm射野深度剂量中的电子线份额为5.3%,40 cm×40 cm射野深度剂量中的电子线份额为15.2%。通过电离室测量和蒙特卡罗计算的方法能够确定X-射线射野的剂量分布特性。     

15MeV医用电子直线加速器治疗室内光核中子辐射场的研究

医用电子直线加速器产生的X射线已广泛的应用于放射治疗过程。由于X射线能量高于某一阈值与周围物质发生(γ,n),(γ,2n)反应而产生光核中子,导致治疗过程中,存在一定程度的中子污染危害。采用Monte-Carlo模拟方法,以点源模型对一台工作在15MeV能量档的Primμs-M型医用电子直线加速器,对照射野在0cm×0cm、3cm×3cm、5cm×5cm、10cm×10cm和20cm×20cm时,使用CR-39固体核径迹探测器和中子气泡探测器(BND)对照射野及照射野外中子剂量分布进行了测量,并对光中子剂量分布进行了模拟。测量和模拟的结果均表明,单一照射野内,光核中子引起的剂量随照射野周长减少呈指数增强趋势。随着照射野面积增大,光核中子总注量逐步增强。采用调强适形放射治疗时,光核中子引起的中子剂量贡献不容忽视。     

Bolus下空腔对放疗浅表剂量和最大剂量点深度的影响

探讨浅表肿瘤放疗时Bolus下空腔对浅表剂量和最大剂量点深度的影响。在Eclipse计划系统里创建30 cm×30 cm×30 cm的体模及体模表面创建10 mm厚的Bolus,设置Bolus和体模材料均为水。在Bolus和体模之间设置0 mm、2 mm、5 mm、10 mm、20 mm、30 mm厚度的Air空腔,将源皮距设置为100 cm,射野面积大小分别取5 cm×5 cm、10 cm×10 cm、15 cm×15 cm、20 cm×20 cm、25 cm×25 cm。剂量大小为100 cGy,获取不同空腔厚度不同射野大小下,体模浅表1 mm深度的剂量(D_s)和体模内最大剂量点的深度值(d_max),同时用德国PTW公司水箱在加速器上做同样条件的实验,用EBT3胶片测量浅表剂量D_s,电离室获取d_max。将计划系统得到的结果和实验测量的结果进行差异对比,结果表明:无Bolus时,计划系统D_s为0,而实验测量D_s有剂量,计划系统和测量结果均显示射野面积大小...     

60Co治疗机散射校正因子的蒙特卡罗计算

利用蒙特卡罗程序MCNP模拟计算了⁶⁰Co治疗机的3种散射校正因子,并计算了总散射校正因子S_c,p与模体散射校正因子S_p随射野及深度的变化。计算结果表明：散射校正因子计算结果与测量结果符合较好;S_c,p与S_p随射野的增大而增大;射野大于10cm×10cm时,S_c,p与S_p有随着深度的增加而增大的总趋势;射野小于10cm×10cm时,S_c,p与S_p有随深度增加而减小的总趋势。因此,在计算处方剂量时不可忽略散射校正因子的影响。利用蒙特卡罗方法可建立1组准确和全面的散射校正因子,为放射治疗临床使用、质量保证和质量控制提供依据。     

6 MV Truebeam治疗头的MC模拟与特性研究

用MC程序EGSnrc准确快速地模拟6 MV Varian Truebeam医用直线加速器治疗头,分析其能谱特性,并验证模拟结果的准确性,为后续更精确的剂量计算建立基础。以Varian公司提供的出束窗口位置处的IAEA相空间文件作为输入源,模拟计算源皮距为100 cm,射野大小为10 cm×10 cm的治疗野平面上的粒子相空间分布,并以此粒子相空间数据为基础进一步模拟计算了边长为30 cm的标准水体模中的剂量分布。通过对数据分析得到了治疗野平面上的粒子能谱、角分布、平均能量、粒子注量等信息,以及均匀水体模中光子的百分深度剂量和离轴比,所得结果与文献报道符合较好。结果表明EGSnrc程序能够准确快速地模拟加速器治疗头,其剂量的模拟计算结果可为临床放射治疗供很好参考。     

HPGe测量连续硬X射线能谱的解谱方法研究

结合数值模拟得到的单能光子在HPGe探测器上能量响应函数，用改进的剥谱法对测量得到的连续硬X射线能谱进行解谱。扣除测量谱中康普顿、反散射等效应产生的计数对测量能谱的影响，得到了仅反映探测器对光电效应的能量响应的能谱。最后，通过效率修正，完成了测量谱到实际能谱的还原,为连续硬X射线能谱解析提供了可靠方法。     

电子调强放射治疗中多叶准直器的研究

电子调强放射治疗浅表肿瘤优于光子调强放射治疗,但光子调强放射治疗中光子的多叶准直器不适用,需专门的电子多叶准直器EMLC。用Monte Carlo模拟计算研究EMLC叶片的材料、厚度、端面形状和宽度等对剂量的影响。计算结果表明,W比Pb、Fe、Cu更适合做EMLC材料,且厚度2cm时足以挡住大部分电子,并产生相对较少的轫致辐射;直立端面作EMLC叶片端面时会产生较小剂量半影,并在射野边缘有更好平坦度;电子束通过宽度5mm的EMLC叶片比1cm的射野边缘剂量明显增加,但宽度太大不利于准确控制子野形状,因此选择1cm作EMLC叶片宽度较优。     

医用发泡胶对粒子剂量影响的模拟研究

目前发泡胶在放疗定位中运用广泛,但其对加速器基础剂量影响并无相关报道。研究不同厚度的发泡胶在医用电子直线加速器均整(Flattening Filter,FF)和非均整(Flattening Filter Free,FFF)两种模式对粒子剂量的影响,为临床使用提供参考。利用蒙特卡罗程序EGSnrc进行建模和计算,首先根据厂家提供的发泡胶参数建立PEGS4材料库与截面数据,利用BEAMnrc建立Varian True Beam系列不同射野的加速器机头模型并进行计算,生成对应的相空间文件;然后利用BEAMdp分析不同模型结构产生的射线能谱、能量注量的差异。最后利用Dosexyznrc计算分析不同厚度发泡胶在固定射野和固定厚度发泡胶在不同射野对粒子剂量的影响。结果表明:在有发泡胶时两种模式下的百分深度剂量(Percentage Depth Dose,PDD)都有不同程度的向前移动的现象,导致表面剂量增加,但对射线则影响不大。FF模式下当发泡胶厚度≤5 cm时,同一深度最大剂量偏差≤2%,而当发泡胶厚度达到10 cm时,同一深度最大剂量偏差高达6%,且两种模式下PDD0都超过90%。在两种模式下发泡胶对射野离轴比和半影都有较大影响,射野越小对粒子剂量影响也越小。临床使用发泡胶时尽量将厚度控制在5 cm以内,当需要使用较厚发泡胶时,建议使用FFF模式;使用立体定向放射治疗时发泡胶对剂量影响不大。     

NaI晶体谱仪采集X射线能谱测量方法研究

为准确测量轫致辐射X射线能谱,利用NaI晶体谱仪对于测量光子的能谱展宽效应,结合理论模拟分析,提出了采用变能量矩阵求解法实现X射线能谱的重建。该方法通过合理选择能量区间,可有效消除能谱响应矩阵中各矢量的相关性,从而实现能谱的准确重建。并分别以均匀能谱分布和实际轫致辐射X射线能谱为例,进行了X射线的能谱重建。获得结果与原始能谱的相关性约为0.98。     

利用EGS4程序对复合耙的初步研究

为了使X射线能谱硬化以利于放射治疗,国外中、高能医用加速器较多采用复合靶技术。本工作利用EGS4程序对复合靶进行了初步研究,模拟了不同能量电子入射到复合靶所产生光子和电子的剂量分布。计算表明：采用结构为2mm厚钨靶片,再加上3mm厚的铜或10mm厚的石墨作过滤片的复合靶后,电子剂量降为仅用钨靶剂量的10％,光子剂量仍保持最佳值,且光子的平均能量得到提高。此复合靶达到硬化X射线和降低电子污染的预期目标。     

On the depth dependence of spallation reactions in a spherical thick diorite target homogeneously irradiated by 600 MeV protons: Simulation of production of cosmogenic nuclides in small meteorites

An artificial meteorite made out of diorite with a radius of 5 cm was irradiated isotropically with 600 MeV protons in order to simulate the production of cosmogenic nuclides in small meteorites by galactic cosmic ray protons. The primary proton dose of 4.82 × 10¹⁵ cm⁻² is equivalent to a some 50 Ma of cosmic ray exposure. The depth dependent production of a wide range of radionuclides from target elements O, Mg, Al, Si, Ti, Fe, Co, Ni, Cu, Ba, and Lu was measured. Furthermore, the production of He and Ne isotopes from Al, Mg, Si, as well as from glass and meteoritic material was determined. Thick-target data are compared with thin-target production rates measured simultaneously, thus allowing to separate the contribution of secondary protons and neutrons. The results demonstrate that, in contrast to present presumptions, even in small meteorites secondary particles have to be considered and that the depth profiles show differences in production of up to 30% between surface and center. The experimental data are discussed with respect to cosmic irradiation conditions of real meteorites. Using Monte Carlo techniques depth dependent nucleon spectra were calculated. On the basis of these spectra and of thin-target excitation functions theoretical production rates were derived and compared with the experimental ones. This comparison shows that it is possible to reproduce the experimental depth profiles quite well by thin-target calculations provided reliable excitation functions are at hand. The thick-target measurements and the thin-target calculations provide a basis for an advanced modelling of the production of cosmogenic nuclides in small meteorites, which strictly differentiates between all contributing production modes.     

低剂量离子在物体样品中透射行为的研究

利用金硅面垒探测器测量低剂量率的Ｆ离子在生物组织样品（洋葱内表皮和芸豆种皮）中的透射能谱,用来研究荷能离子在生物样品中的能损和深度分布,实验中Ｆ离子能量为９００ｋｅＶ－６ＭｅＶ剂量率大约为１０＾４ｉｏｎｓ／ｓ·ｃｍ＾２。用ＳＥＭ观测样品在离子束轰击下可能发生的损伤,实验中测量了了不同能量离子样品中的透射能谱,利用ＳＩＮＲＡ对测量得到的透射能谱进行了拟合分析,并讨论了生物样品的特殊结构对透射能谱和离     

The relation between depth and energy in channeling experiments

Spectra of protons backscattered from a silicon single crystal were measured at a bombarding energy of 2300 keV. A narrow resonance in the elastic scattering cross sections of protons from ²⁸Si, at 2090 keV, shows up as a peak in the spectra. The position and the shape of this peak were found to vary when the beam alignment was changed from a random to an axial or planar crystal direction. These effects are attributed to a different energy loss distribution of the incoming protons in these three cases. The measured spectra were compared with spectra obtained from Monte Carlo simulations in which the dependence of the energy loss on the impact parameter of the collision is taken into account. The measured and simulated spectra were found to agree qualitatively. By analysing the energy loss of the simulated trajectories, conclusions are drawn about the influence of the reduced energy loss in channeling directions on the energy to depth conversion in channeling experiments.     

Field photon energy spectra in Fukushima after the nuclear accident

After the accident of the Fukushima Daiichi Nuclear Power Plant, radionuclide were spread out over large area. It has been past almost two years since the nuclear accident. Therefore, Cs-137 and Cs-134 nuclei are the main sources of gamma rays. The field gamma rays, however, are not mono-energy due to photons scattered from the ground, the air, etc. The effective dose for external exposure depends on the energy of radiations, thus photon energy spectra are important for the evaluation of effective dose for the people who live in Fukushima. In the present study, the photon energy spectra have been measured at several points in Fukushima to evaluate reference energy spectra after the nuclear accident. The energy spectra in Fukushima area were measured using a cadmium zinc telluride (CdZnTe) detector, and an unfolding method was applied to evaluate photon energy spectra. The fraction of low-energy photon is increased by decontamination around the measurement point. This can be used to estimate the efficiency of decontamination effect by removing the radionuclides on the target surface. The photon energy spectra measured by the present study would be useful for the evaluation of the effective dose for the people who live in Fukushima.     

Deconvolution of neutron depth profiling spectra

Iterative methods for determining deconvolued depth profiles from measured neutron depth profiling (NDP) energy spectra are presented. The methods account for energy broadening caused by system noise, energy straggling, multiple small angle scattering, and geometrical acceptance angles. Examples of the methods are given for known and unknown profiles of helium-3 and nitrogen-14.     

基于N型同轴HPGe探测器获取过滤X射线注量谱

构建ISO 4037?1以外的过滤X射线参考辐射需射束注量谱计算平均能量、分辨率和转换系数等参数。为建立过滤X射线注量谱获取方法,采用N型同轴HPGe探测器测量了N?40?N?250窄谱系列过滤X射线参考辐射并得到了脉冲幅度谱,使用Geant4模拟了探测器对放射源的响应并用实测能谱进行了验证,进而建立了响应矩阵,并通过MAXED软件解谱计算得到了射束的注量谱。由解谱所得注量谱计算的空气比释动能到周围剂量当量和个人剂量当量的转换系数与ISO 4037?3推荐值的相对偏差在0?06%?2?55%之间。     

Measurement and Simulation of TEPC Microdosimetric Spectra in Gamma Radiation Field

According to the different characteristics of microdosimetric spectra measured by tissue equivalent proportional counter (TEPC), the neutron dose equivalent and γ dose equivalent could be distinguished in a unknown neutron and γ mixed radiation field. In order to discriminate the γ radiation dose equivalent from the total value,the pure γ microdosimetric spectra was measured in ⁶⁰Co、¹³⁷Cs radionuclide radiation field with TEPC. TEPC microdosimetric spectra in a series of monoenergy γ radiation field were simulated by FLUKA code. All the γ radiation microdosimetric spectra, including measured spectrum in ⁶⁰Co、¹³⁷Cs radiation field and that of simulation spectrum by FLUKA code, reveal a trait that the linear energy of γ radiation is basically lower than 10 keV/μm. This trait is the very foundation to discriminate the γ radiation from the mixed radiation.     

The neutron tissue dose

This paper is devoted to the determination of dosimetric characteristics of intermediate-energy neutrons. A calculation of the interaction of neutrons with paraffin for the normal incidence of an extended beam of neutrons in the energy interval from 100 ev to 1 Mev, which has been performed by means of an electronic computer, is given here. The computation results are used for calculating the components of the neutron tissue dose resulting from the moderation process in the tissue. The dose resulting from the neutron capture is calculated on the basis of the authors' data on the distribution of slow neutrons in paraffin and on neutron reflection from the surface of a hydrogenous medium. The depth distributions of neutron dose components for thermal neutrons and neutrons with energies of 100 ev, 1, 30, 240, 500 kev, and 1 Mev were obtained. The depth distributions of the biological dose for neutrons of the same energy and the biological dose values pertaining to the unit neutron flux were obtained.     

能谱-剂量转换法用于环境辐射剂量测量

为准确测量环境水平剂量率,基于无卷积全谱转换法,通过测量X/γ能谱和剂量率,开展能谱-剂量转换系数求解并实现能谱-剂量的转换。结果表明,能谱-剂量法计算剂量率与实测剂量率的残差近似为0,证明该方法在能谱-剂量求解过程自洽;在¹³⁷Cs、⁶⁰Co标准参考辐射场下的剂量率线性测试结果与标准值的最大相对误差为±10%,表明无卷积全谱转换法用于能谱-剂量转换系数的求解可行。     

核电厂运行现场高能γ射线的剂量调查

在核电厂正常运行期间,反应堆冷却剂系统内存在能够发射高能γ射线的¹⁶N等放射性核素。为了初步掌握核电厂运行期间不同区域内高能γ射线的辐射水平,利用NaI(Tl)谱仪在国内某核电站测量了反应堆厂房内的γ能谱,并根据γ测量谱和测量系统的响应函数计算了能量大于3 MeV的γ射线的场所剂量率。结果显示:在15个测量位置中,6个位置的γ测量谱中存在明显的高能成分,其对应的剂量率在1.02～30.14 μSv/h范围内。