北京地区医用加速器高能光子水吸收剂量398、277报告的量值验证

针对我国放疗水吸收剂量测量方法即将更新的现状,先后在北京多家医院放疗科的医用加速器下进行了200多次高能光子水吸收剂量量值验证实验。按照IAEA 277报告和IAEA 398报告的测量方法,测量高能光子最大剂量点处的水吸收剂量值并进行比较。统计2种方法测量结果的偏差,在NE2571电离室的实验结果中,398报告的测量结果比277报告的测量结果大0.23%;在PTW30013电离室的实验结果中,398报告的测量结果比277报告的测量结果测量结果大0.85%。实验表明,2种方法的测量结果在不确定度范围内一致,实验为398报告量值体系在我国的推行建立了实验基础。对结果的偏差做了分析,深入研究了相关因子的计算过程,从几个修正因子的角度探讨了偏差产生的原因。     

基于IAEA TRS398报告的加速器水吸收剂量测量方法

研究用IAEA TRS398的方法测量高能X射线和高能电子的水吸收剂量的测量方法和计算过程。按照398报告的对位和测量方法获得测量值,根据辐射质和电离室型号计算得到的k_(Q,Q0),测得各辐射质的PDD曲线,求出最大剂量点处的水吸收剂量,并与277报告的计算结果进行比较。在6MV、10MV高能X射线、18MeV高能电子下,按照398报告和277报告的方法测得最大剂量点处剂量分别为2. 251、2. 676、2. 243(Gy)和2. 251、2. 669、2. 254(Gy),相对偏差为0. 00%、0. 26%、-0. 49%。两种方法测量结果在不确定度范围内一致,且398方法更易于操作和计算。     

基于水吸收剂量校准因子的应用与分析

基于中国计量科学研究院(NIM)给出的水吸收剂量校准因子对江苏省内40台医用直线加速器的绝对剂量进行了测量,结果表明PTW 30013型电离室的射束质转换因子分别参考NIM的校准值和IAEA TRS 398号报告时的和计算值,相比较差异最大为0. 6%,对的计算结果影响较大。     

医用高能光子水吸收剂量测量规范TRS-277与TRS-398比较

随着吸收剂量测量及其量值溯源理论和技术的发展,国际原子能机构先后发布了TRS-277、TRS-398号报告,规范了高能光子水中吸收剂量的测量,以满足临床应用时不确定5.0%(k=2)的要求.文中依据两个报告,从量值溯源方式、测量方法、参数引用、修正因子的来源及其确定等方面,比较了两个报告在高能光子水中吸收剂量测量中的使用差异;同时指出了应用TRS-398号报告能进一步减少测量结果的不确定度,对开展精确放射治疗具有指导意义.     

医用电子束吸收剂量测量中的平行板电离室校准

基于平板电离室的结构和物理特性,比圆柱形电离室更适用于电子束的水中吸收剂量测量,特别是在能量相对较低的电子束测量中更具优越性.介绍了基于两种量传体系的平板电离室溯源方式,提出了在现场如何利用已知校准因子的参考电离室得到平板电离室的校准因子的方法.在国内尚未建立水吸收剂量量传体系时,借助该方法可获得平板电离室水吸收剂量校准因子,据此按照TRS-398报告开展高能电子束水中吸收剂量测量,进一步减小测量结果的不确定度.     

IAEA TRS-398临床剂量学应用

为降低临床放射治疗剂量测量的不确定度,讨论并对比了直接测量处方剂量:水吸收剂量的方法TRS-398报告应用于临床的优势。通过介绍在不同种类射线下直接测量水吸收剂量的条件与方法,汇总目前基于TRS-398报告测量方法的部分实验数据,结果表明:TRS-398报告方法测量剂量与277报告方法测量剂量在允许测量不确定度以内一致,表明398报告方法测量结果可靠,且满足临床剂量输出不确定度5%(k=1)以内的要求。这一结果为更新临床放射治疗剂量输出测量的方法提供理论依据。     

国家吸收剂量标准(~(60)Co γ射线)—Fricke剂量计

为了建立医学、农业和辐射加工(~60Co γ射线)吸收剂量国家标准,精确测定了Frieke剂量计中Fe~(3+)离子摩尔消光系数ε_m值,着重研究了邮寄玻璃安瓿剂量计的制备方法和工艺,采用老化和预辐照剂量计溶液的办法进行质量控制,有效地清除了有害杂质的影响,使未辐照剂量计的本底读数十分稳定,提高了测量精度。同时,试验观察了影响吸收剂量测量的一些因素;考查了剂量计的复现性和长期稳定性;并进行了医用(限束)和工、农业(非限束)~(60)Co γ射线水模体中校准点处吸收剂量的测量以及与标准照射量计(Farmer 2560)的比对。结果表明,在测定~(60)Co γ射线(限束与非限束)水中吸收剂量量值,当剂量范围为(40～400)Gy时,测量的重复性有效地控制在±1.0％以内(95％置信度),总不确定度在±1.9％以内。     

平行板电离室的检定与测量

本文较详细介绍了国际原子能机构（IAEA）第381号报告中60Coγ射线-空气法检定平行板电离室的方法和水中吸收剂量的测量,并对平行板电离室检定与测量进行讨论.     

用于~(60)Coγ射线照射量基准的石墨空腔电离室的研制

本文报告了一种用于γ射线照射量基准的石墨空腔电离室,采取球-圆柱形状,结构设计和材料选择保证了电离室良好的测量性能和稳定性。采用水称重法和几何尺寸测量相结合。精确测定了电离室体积。电离室内电场的合理分布,保证了可以得到良好的饱和特性。根据“等效壁厚”来考虑室壁的减弱效应,采用对“等效壁厚”外推的方法来得到室壁修正。用此电离室进行~(60)Co γ射线照射量测量的标准化,得到了满意的结果。测量照射量的合成不确定度为±0.25％。与BIPM的~(60)Co γ射线照射量测量比对,结果在0.16％以内一致,     

AAPM TG-51临床参考剂量学的特点及应用

本文介绍了AAPM (美国医学物理家协会 )TG - 5 1号新报告 ,即“高能光子和电子束参考剂量学议定书”。它是以60 Coγ射线在水中的吸收剂量直接校准治疗水平电离室型剂量计 ,然后根据临床应用的射束辐射质再计算水中的吸收剂量。它是辐射剂量学中的一项重大改进 ,这种方法易于理解 ,执行方便 ,精确度高。     

水量热法加速器光子水吸收剂量绝对测量与国际比对

为实现加速器光子水吸收剂量绝对测量,研制了水量热计系统,在此基础上取得国际互认并建立加速器光子水吸收剂量基准,进一步提高了我国放疗剂量量值传递能力。通过水浴与半导体制冷系统二级控温,将量热计水模体的温度漂移控制在0.5μ℃/s。利用惠斯通交流电桥测量辐射所致的热敏探针阻值变化,逐次校准热敏探针和交流电桥,实现了医用加速器光子水吸收剂量的绝对测量,合成标准不确定度为0.30%。参加了国际计量局加速器光子水吸收剂量关键比对,复现的6MV和10MV光子水吸收剂量值与比对参考值之比分别为0.9917和0.9949,在不确定度允许的范围内一致。     

医用加速器光子水吸收剂量国际比对及进展

医用加速器光子水吸收剂量国际比对采用星式比对方式,主导实验室为国际计量局,其石墨量热计复现的水吸收剂量为比对参考值.各国计量实验室依据各自医用加速器辐射质参数,进行2～3个辐射质的水吸收剂量绝对测量,现已完成7个国家的比对工作,比对数据公布在关键比对数据库中.     

γ射线辐照对PA6/PTFE合金吸水与力学性能的影响

为了探讨辐照对尼龙6(PA6)基共混材料吸水性能和力学性能的影响,制备了PA6和聚四氟乙烯(PTFE)共混合金并在室温下进行不同剂量的60Coγ射线辐照.通过吸水率测试、准静态拉伸和弯曲实验以及缺口冲击测试,研究了辐照对PA6/PTFE共混体系吸水性能以及吸收水和辐照剂量对共混合金动静态力学性能的影响.结果表明,辐照过程引发交联反应,共混合金的拉伸强度、拉伸模量和弯曲模量均随辐照剂量的增大而增大,而缺口冲击强度和吸水率则随之减小.吸收水对共混合金缺口冲击强度的影响与合金组分有关.PTFE含量较低时,吸收水抑制PTFE对合金冲击强度的减弱作用;当PTFE的质量分数大于7%时,吸收水反而加剧PTFE对材料冲击强度的减弱效应.此外,PA6/PTFE合金的吸水率随PTFE含量的增加而降低,而弯曲模量则先增后减.     

Dosimetry of clinical neutron and proton beams: an overview of recommendations

Neutron therapy beams are obtained by accelerating protons or deuterons on Beryllium. These neutron therapy beams present comparable dosimetric characteristics as those for photon beams obtained with linear accelerators; for instance, the penetration of a p(65)+Be neutron beam is comparable with the penetration of an 8 MV photon beam. In order to be competitive with conventional photon beam therapy, the dosimetric characteristics of the neutron beam should therefore not deviate too much from the photon beam characteristics. This paper presents a brief summary of the neutron beams used in radiotherapy. The dosimetry of the clinical neutron beams is described. Finally, recent and future developments in the field of physics for neutron therapy is mentioned. In the last two decades, a considerable number of centres have established radiotherapy treatment facilities using proton beams with energies between 50 and 250 MeV. Clinical applications require a relatively uniform dose to be delivered to the volume to be treated, and for this purpose the proton beam has to be spread out, both laterally and in depth. The technique is called 'beam modulation' and creates a region of high dose uniformity referred to as the 'spread-out Bragg peak'. Meanwhile, reference dosimetry in these beams had to catch up with photon and electron beams for which a much longer tradition of dosimetry exists. Proton beam dosimetry can be performed using different types of dosemeters, such as calorimeters, Faraday cups, track detectors and ionisation chambers. National standard dosimetry laboratories will, however, not provide a standard for the dosimetry of proton beams. To achieve uniformity on an international level, the use of an ionisation chamber should be considered. This paper reviews and summarises the basic principles and recommendations for the absorbed dose determination in a proton beam, utilising ionisation chambers calibrated in terms of absorbed dose to water. These recommendations are based on the recent IAEA TRS398 Code of Practice: 'Absorbed Dose Determination in External Beam Radiotherapy: An International Code of Practice for Dosimetry based on Standards of Absorbed Dose to Water'.     

Photon beam audits for radiation therapy clinics: a pilot mailed dosemeter study in Turkey

A thermoluminescent dosemeter (TLD) mailed dose audit programme was performed at five radiotherapy clinics in Turkey. The intercomparison was organised by the University of Wisconsin Radiation Calibration Laboratory (UWRCL), which was responsible for the technical aspects of the study including reference irradiations, distribution, collection and evaluation. The purpose of these audits was to perform an independent dosimetry check of the radiation beams using TLDs sent by mail. Acrylic holders, each with five TLD chips inside and instructions for their irradiation to specified absorbed dose to water of 2 Gy, were mailed to all participating clinics. TLD irradiations were performed with a 6 MV linear accelerator and (60)Co photon beams. The deviations from the TL readings of UWRCL were calculated. Discrepancies inside the limits of ±5 % between the participant-stated dose, and the TLD-measured dose were considered acceptable. One out of 10 beams checked was outside this limit, with a difference of 5.8 %.     

Preparation and Characterization of Fe3O4 Magnetic Nano-particles by 60Co γ-ray Irradiation

By using a new method, ^60Co γ-ray irradiation, Fe3O4 magnetic nano-particles were successfully synthesized at room temperature under ambient pressure. The structure, morphology and magnetic properties of these nanoparticles were characterized by X-ray diffraction （XRD）, transmission electron microscope （TEM） and vibrating sample magnetometer （VSM）, respectively. The radiation formation mechanism was also discussed. The results show that the absorbed dose can greatly influence the structure, morphology and magnetic properties of the products. XRD and TEM studies show that the product prepared by γ-ray irradiation （10 kGy） is pure FesO4 phase and the mean diameter of these nano-particles is about 21 nm. The Fe3O4 nano-particles synthesized by γ-ray irradiation （10 kGy） are mainly in small cubic shape and the size uniformity of these particles is good.     

Nationwide Survey of 60Co Teletherapy Dosimetry

The National Bureau of Standards is performing a study of the ability of radiation-therapy departments to deliver prescribed absorbed doses of ⁶⁰Co gamma radiation to a water phantom. Batches of thermoluminescence dosimeters are mailed to participating therapy departments for irradiation under prescribed conditions. Upon return of the dosimeters, the participants’ computations are checked and the absorbed dose is evaluated from dosimeter response. The rugged dosimetry system was assembled mainly from commercial components adapted to the present requirements of relatively high flexibility of readout parameters and data-handling techniques, and of relatively high accuracy. The uncertainty in the dose interpretation inherent in the system is estimated to be about 4 percent.In order to illustrate the type of information that can be obtained from such a study, results of the first four mailings involving tests on 114 ⁶⁰Co gamma-ray beams are discussed. They show about 75 percent of the dose interpretations to be within 5 percent of the prescribed absorbed dose, and about 20 percent to be within 5 to 10 percent of this dose. Four dose interpretations showed discrepancies larger than 20 percent. Differences in the computations larger than 1 percent were observed in over one-half of the cases.     

Re-evaluation of correction factors of a primary standard graphite calorimeter in 60Co gamma ray beams as a basis for the appointment of the BEV absorbed dose rate to water reference value

The graphite calorimeter of the Federal Office of Metrology and Surveying (BEV-Bundesamt für Eich- und Vermessungswesen) was established in the 1980s as the primary standard for the absorbed dose to water for (60)Co gamma ray beams. To maintain the primary standard at an international level the graphite calorimeter and its corresponding components had to undergo a refurbishment and modernisation process. The correction factors of the graphite calorimeter were re-evaluated with Monte Carlo and experimental methods to obtain improved values. These are the correction for the effect of the gaps (1.0061), the scaling correction (0.9998), the correction for the difference in air attenuation (0.9971) and the corrections for the effective measurement depths in the graphite phantom for the graphite calorimeter (0.9886) and the CC01-105 ionisation chamber (0.9913). Consequently, it was necessary to change the reference value for the absorbed dose rate to water of the (60)Co teletherapy unit used for the calibration of secondary standard dosemeters.