Experimental determination of the absorbed dose to water in a scanned proton beam using a water calorimeter and an ionization chamber

The absorbed dose to water is the reference physical quantity for the energy absorbed in tissue when exposed to beams of ionizing radiation in radiotherapy. The SI unit of absorbed dose to water is the gray (Gy = 1 J/kg). Ionization chambers are used as the dosimeters of choice in the clinical environment because they show a high reproducibility and are easy to use. However, ionization chambers have to be calibrated in order to convert the measured electrical charge into absorbed dose to water. In addition, protocols require these conversion factors to be SI traceable to a primary standard of absorbed dose to water. We present experimental results where the ionization chamber used for the dosimetry for the scanned proton beam facility at PSI is compared with the direct determination of absorbed dose to water from the METAS primary standard water calorimeter. The agreement of 3.2% of the dose values measured by the two techniques are within their respective statistical uncertainties.     

Monte carlo study on 6 MV photon beams of a CyberKnife(R) stereotactic radiosurgery system

In this paper, the beam quality and percent depth dose curves for different field sizes of Cyber Knife(R) system were investigated by Monte Carlo simulations using the PENELOPE code, which has been used to simulate 6 MV photon beam. In water phantom, the absolute doses were calculated for φ10-60 mm collimators, and percent depth dose curves were evaluated for φ30-60 mm collimators. The agreement ofdose distributions of the calculation with measurement was within 3.0%. The mean energy ofphoton spectrum was 1.46 MeV, and the beam quality index was 0.632, which was slightly smaller than that ofmeasurement.     

空腔理论在固体剂量计中的应用

在Burlin空腔理论基础上提出了1个经修改后可适用于兆伏级X(γ)能量固体剂量计的新空腔理论。它通过Monte-Carlo方法分别计算固体剂量计空腔内的初级光子粒子注量和散射光子粒子注量及它们相应产生的次级电子粒子注量，并按空腔尺寸所对应的电子射程，把高能和低能光子分开，计算初级光子和散射光子沉积在固体剂量计灵敏体积中的能量，即吸收剂量。为验证该空腔理论，用半导体固体剂量计在6MV医用电子直线加速器上进行了水模体输出因子测量，并模拟相同测量条件用新空腔理论对水模体输出因子进行了理论计算，其测量结果与计算结果在0.5%内符合。     

CR-39 detector based thermal neutron flux measurements, in the photo neutron project

PhoNeS (photo neutron source) is a project aimed at the production and moderation of neutrons by exploiting high energy linear accelerators, currently used in radiotherapy. A feasibility study has been carried out with the scope in mind to use the high energy photon beams from these accelerators for the production of neutrons suitable for boron neutron capture therapy (BNCT). Within these investigations, it was necessary to carry out preliminary measurements of the thermal neutron component of neutron spectra, produced by the photo-conversion of X-ray radiotherapy beams supplied by three LinAcs: 15 MV, 18 MV and 23 MV. To this end, a simple passive thermal neutron detector has been used which consists of a CR-39 track detector facing a new type of boron-loaded radiator. Once calibrated, this passive detector has been used for the measurement of both the thermal neutron component and the cadmium ratio of different neutron spectra. In addition, bubble detectors with a response highly sensitive to thermal neutrons have also been used. Both thermal neutron detectors are simple to use, very compact and totally insensitive to low-ionizing radiation such as electrons and X-rays. The resultant thermal neutron flux was above 10⁶ n/cm²s and the cadmium ratio was no greater than 15 for the first attempt of photo-conversion of X-ray radiotherapy beams.     

放射治疗剂量验证中常用剂量分布比较方法及分析

使用非晶硅平板探测器(Amorphous silicon electronic portal imaging device,a-Si EPID),在源-探测器距离100 cm处,用6 MV的光子束照射采集3个不同大小射野的剂量图,将该数据分割为4个区域,并对每个区域数据进行不同条件下的修改来构建模型,然后用放射治疗剂量验证中常用的3种剂量分布比较方法进行分析。结果表明:百分剂量差比较法对剂量梯度大的区域较敏感,微小的位置偏移会造成较大误差,其适用于剂量分布相对平缓的区域。DTA(Distance-to-agreement)分析法对剂量分布平缓的区域较为敏感,微小的剂量差异也会造成较大的误差,其适用于剂量梯度相对陡峭区域。γ分析法则结合了剂量差异分析法与DTA分析法的优点,不管对于剂量梯度较大区域还是平缓的区域,其计算值不会过大,误差较小,能更好地用于临床剂量验证。     

辐射剂量学实验室的质量保证研究

作为国际原子能机构协作研究项目的分课题之一，对辐射剂量学实验室的内部质量控制试验、剂量比对研究、中国规程与国际原子能机构(IAEA)规程的比较研究、不确定度的评估、校准量的转变、以及质量保证手册等诸方面给出了实验结果，并进行了讨论。     

Monte Carlo Calculations of Irradiation Test Photon Spectra

Calculations of scattered photon spectra in concrete rooms are made, by means of the Monte Carlo method, for Co-60 sources of the type used in irradiation testing of electronic devices. It is found that the scattered photon spectrum shape is heavily dependent on the location of source and target, and that in devices where dose enhancement can occur, there can be substantial variation in the absorbed dose due to this strong dependence on location. Scattered photon spectra are also obtained for two types of irradiation test cells. Additionally, dose enhancement ratios obtained with a coupled photon-electron Monte Carlo calculation are given for a gold-metallized silicon device.     

西门子直线加速器均整和未均整射束的光子束剂量学特性

利用BEAMnrc和DOSXYZnrc蒙特卡罗程序研究西门子直线加速器6 MV能量均整和未均整光子束的剂量学特点。比较两种射束的深度剂量分布、离轴比剂量分布、中心轴剂量率和总散射因子。结果表明,未均整射束各射野的百分深度剂量均比均整射束的低;中心轴剂量率比均整射束大,且两种射束中心轴剂量率比值随射野和深度的增加逐渐下降;除此之外,未均整射束的半影宽度及总散射因子随深度的变化趋势均比均整射束小。未均整射束的剂量学优势可用于临床应用。     

Depth Smoothing of the Dose under Irradiation by Electrons

Irradiation uniformity is an important problem in radiation technology employing electron beams. One variant of a solution of this problem is the use of filters partially covering the primary beam. A method for optimizing the filter parameters is presented; the method used is the modern certified code package PENELOPE. The influence of filter material on the radiation utilization coefficient of a linear electron accelerator is investigated. For processing of polyethylene with a 6 MeV electron beam, filter parameters giving a high uniformity of the depth distribution of the absorbed dose in the material are obtained.     

电子束吸收剂量量热计

研制了一种用于电子束吸收剂量深度分布和电子束能量测量的多层石墨量热计及一种用于吸收剂量测量和薄膜剂量计校准的石墨量热计校准装置,并介绍了两种量热计的结构和在中国原子能科学研究院14MeV加速器上的研究结果。     

MeV能量Si~+引起二次离子发射的研究

利用北京大学2×1.7 MV串列加速器终端的飞行时间(TOF)谱仪,分别用1.5、2.0和3.0MeV三种能量的初级束Si+轰击样品来研究其二次离子发射现象,使用的样品包括石墨、碳纳米管等。结果表明,采用合理的降噪方法后得到了高信噪比和高时间分辨率的二次离子质谱,实现了全质量范围无遗漏记谱。利用H-C12峰刻度之后,计算得出二次离子各成分的最可能构成及产额,碳纳米管样品表面氢质量含量为8.15%。同时,发现MeV能区二次离子产额与Si+阻止本领之间的关系并非简单的正相关。     

Plastic scintillator investigations for relative dosimetry in proton-therapy

Plastic organic scintillators, polyvinyltoluene based, can be used with high sensitivity to detect 1–60 MeV proton beams. Thin scintillators can be applied to proton-therapy field as relative dosimeter thanks to their water-equivalent nature, high energy–light conversion efficiency, low dimensions and good proportionality to the absorbed dose at low stopping powers. Unfortunately, the quenching effect limits the use of the scintillators at high stopping powers. Moreover, they show a negligible radiation damage at the typical proton doses used in radiotherapy. Preliminary results have been obtained detecting in air both 60 MeV therapeutically proton beam at the Paul Scherrer Institute (PSI, Villigen-Zurich) and 24 MeV proton beam, at the Laboratorio Nazionale del Sud (LNS, Catania).     

Dose intercomparison studies for 60Co gamma-ray and electron beam irradiation in the year 2002

1 Introduction With the rapid development of radiation process- ing by electron beam irradiation in China, it is more Ever since 1962, alanine/EPR dosimetry system and more needed to establish a transfer dosimetryhas been used to measure the absorbed dose.[1] Its ad- system with high accuracy to assure the quality of thevantages over othe…     

女性蹲姿曲面模型光子外照射剂量研究

基于中国女性参考人曲面模型建立女性蹲姿曲面模型,采用蒙特卡罗方法,针对6种标准光子外照射几何,计算光子能量0.01～10 MeV范围内21个能量点的器官吸收剂量转换系数和有效剂量转换系数,并与直立姿势的剂量数据进行了对比。结果表明:两种姿势中某些器官的吸收剂量转换系数在前后、后前以及侧向照射方式下差异较大。其中,后前照射方式下,光子能量为0.03 MeV时,乳腺的吸收剂量转换系数比直立姿势高115.1%。在不同照射方式下,大部分能量点的有效剂量转换系数的差异在10%范围内。转换系数的差异主要是由于胳膊和腿位置的改变,以及蹲姿时因身体前倾造成器官在照射方向上厚度发生改变而产生的。     

用于硼中子俘获疗法治疗束的光子谱仪设计

实验确认治疗束的谱源项参数是硼中子俘获治疗（BNCT）物理剂量学研究的重要环节之一,全面细致地掌握相关信息,对精准制定临床治疗计划进而准确评估患者的给予剂量十分重要。为验证理论计算源项光子能谱的可靠性,设计适用于BNCT治疗束特点（宽能量范围、高强度n/γ混合束）的新型光子谱仪。通过蒙特卡罗模拟方法优化探测器内的中子注量率、光子计数率及次级光子占比（次级光子计数率/初级光子计数率）三个重要参数,在降低辐射强度以避免探测器的辐射损伤和死时间过大的同时,尽可能抑制中子诱导次级光子的产生,将次级光子占比降至5.45,以实现BNCT治疗束光子谱的快速准确测量。同时,开展谱仪对不同能量光子响应的校准方法研究,以便得到准确的响应函数,为光子谱的解谱工作奠定基础。     

15 MeV～3 GeV电子加速器90°方向光子源项研究

韧致辐射光子是电子加速器屏蔽设计中的重要源项。为研究90°方向光子源项特征以及靶体半径和厚度对90°方向光子源项的影响,采用蒙特卡罗程序MCNPX27对15 MeV～3 GeV电子束轰击铁靶后的辐射源项进行计算。分析了90°方向光子辐射剂量、光子能谱等源项随靶厚度和半径的变化。通过与0°方向光子源项以及靶体内级联电子沉积能量进行对比,进一步分析了90°方向的光子源项特点。结果表明,90°方向光子能量主要集中在10 MeV以内,光子能谱形状与入射电子能量关系较小。受级联电子在靶内能量沉积程度及靶体对光子自吸收的共同影响,靶体半径和厚度是影响90°方向光子源项的重要因素。在电子加速器的屏蔽设计中应考虑靶体尺寸差异所带来的影响,同时建议针对束流90°方向和0°方向光子源项的差异,对加速器辐射屏蔽和防护进行优化设计。     

高剂量水平吸收剂量测量用辐射变色薄膜剂量计研究

为建立制备高剂量水平吸收剂量测量的辐射变色薄膜剂量计的方法,对相应的配方及制备工艺进行研究,批量制备了以尼龙为基材,副品红氰化物为染料的辐射变色薄膜剂量计。在60 Coγ参考辐射场中对辐射变色薄膜的各剂量学响应性能进行了研究,结果表明,重复性好于1.0%,在5~210kGy剂量范围内具有较好的剂量响应线性,辐射变色薄膜剂量计辐照后置于低温条件下贮存2周内信号较稳定。此外,该辐射变色薄膜剂量计在本实验范围内未发现明显的剂量率依赖性。通过上述剂量学性能研究,在线性剂量范围内,测量吸收剂量的扩展不确定度为4.2%(k=2)。通过在加速器上进一步实验表明,该膜可用于电子束辐照参数测量。     

Relations Between the Effective Dose and the Indications of an Individual Dosimeter in Anisotropic Photon Fields

The effective dose, the personal dose equivalent, and the indications of an individual dosimeter are calculated, using the ROBOT computer program (Monte Carlo method), for the conditions of irradiation of an anthropomorphic heterogeneous ICRP phantom with wide beams of 40 keV–11 MeV photons for all solid angles. In anisotropic photon fields, the dosimeter indications satisfactorily estimate the personal dose equivalent. The dependence of the ratio of the effective dose to the indications of an individual dosimeter on the irradiation conditions is analyzed. It is noted that the individual dosimeter indications are not conservative when the phantom is irradiated from the back half-space. It is shown that for wide photon beams the ratio of the effective dose to the dosimeter indications determined neglecting the scattering of radiation inside the working room is an upper limit of the indicated ratio calculated taking scattering into account.     

辐射加工级电子束吸收剂量量热计的研制

叙述了辐射加工级电子束吸收剂量量热计的设计原理,给出了用自行研制的石墨和盒式水量热计测定电子束吸收剂量的方法和结果。用不同吸收体材料和几何参数是热计测量参考材料的吸收剂量,所得结果在０．８％以内符合。并对现有的吸收剂量深度分布测量模体的关键结构作了改进。由测量结果刻度ＧＡＦ－ＤＭ－１２６０和ＦＷＴ－６０辐射显色薄膜得到的电子束吸收剂量响应曲线与＾６０Ｃｏγ射线响应一致。研制的量热计及其测试技术可作