后装治疗源192 Ir空气比释动能强度检测 与评价

目的 研究用井型电离室测量后装192Ir源空气比释动能强度的方法.方法 用CDX-2000A静电计和HDR 1000井型电离室,现场检测30台后装192Ir源空气比释动能强度,根据源外观活度与空气比释动能强度转换系数,计算源外观活度.用实测源活度与厂家给出的初始源活度比较,相对偏差应在±5%内符合要求.结果 对所有检测的30台后装192Ir源活度与厂家初始源活度比较,相对偏差在-0.1%～4.4%范围内.结论 井型电离室测量法简便,准确度高,在医院可用于质量控制检测.

Abstract：

Objective To study the method of measuring air kerma strength of afterloading units with 192Ir source by using well type ionization chamber.MethodsThe air kerma strength of 30 afterloading units with 192Ir source was measured using 2000A electrometer and 1000 plus well type ionization chamber,and apparent activity of the source was calculated with the air kerma strength and apparent activity conversion factor.The measured activity of the source was compared with the original value of the source provided by the manufacturer,and the relevant deviation should be within ± 5%.Results Theair kerma strength of afterloding units with 192Ir sources was tested.The relevant deviation of the measured activity and the original value was within -0.1%-4.4%.Conclusions The measurement method with a well type ionization chamber is convenient and highly accurate which can be used for the test of quality control in hospitals.     

MatriXX射野角度剂量响应修正

Objective To characterize angular dependency of MatfiXX and develop a method for its calibration in order to verify treatment plan with original gantry angles.Methods Absolute dose calibration was carried with thimble ionization chamber on the linear accelerator.so as to make sure 1 MU=1 cGy at the depth of maximum dose(dmax).A MatriXX was put into a Mutlicube phantom,and the ionization chamber matrix was calibrated with absolute dose.In order to determine a correction factor CF as a function of gantry angle θ.open beam fields of 10 cm×10 cm size were irradiated for gantry angles θ=0°-180°(every 5°)and every 1°for lateral angles θ in the range of 85°-95°.CF was defined as the ratio of the dose measured with ionization chamber and the dose from MatriXX.Results Relatively large discrepancies in response to posterior VS.anterior fields for MatriXX detectors(up to 10%)were found during the experiment and relatively large variability of response as a function of gantry angle.The pass rate of treatment plan in lateral beams was lower than that of other beams.The isodose distribution of corrected MatriXX matched well with the outcome from the treatment planning system. Conclusions The angular dose dependency of MatriXX must be considered when it is used to verify the treatment plan with original gantry angles.     

MatriXX射野角度剂量响应修正

目的 对MatriXX探头不同角度剂量响应进行刻度,从而以实际治疗角度对治疗计划进行剂量验证.方法 首先用指形电离室对直线加速器进行绝对剂量校准,使在最大剂量点深度处1 MU=1 cGy.将MatriXX放置在Mutlicbue模体里,并对电离室矩阵进行绝对剂量刻度之后,机架从0°开始每隔5°(在侧野方向间隔1°)对加速器出束测量,记录MatriXX电离室矩阵中心点的剂量.按相同的步骤用电离室测量固体水模体中相同深度处中心点的剂量.电离室测量的剂量和Matrixx测量中心点剂量的二者比值即是MatriXX对不同射野角度的剂量响应修正系数.结果 射野角度剂量响应修正因子随机架角度缓慢的变化,但在侧向角度变化的梯度比较大,从前后到后前方向时,最大变化达10%.治疗计划在侧野方向上的通过率相对其他角度射野要低.MatriXX矩阵经过角度修正后的测量结果的γ通过率相比修正前有较大提高,经过修正后的MatriXX测量结果与计划系统生成的结果在等剂量曲线上吻合很好.结论 如果用MatriXX在不治疗角度不归0位进行治疗计划验证的时候,必须要考虑到角度修正系数,同时将角度修正系数叠加到测量结果再与计划比较的方法也是可行的.

Abstract：

Objective To characterize angular dependency of MatfiXX and develop a method for its calibration in order to verify treatment plan with original gantry angles.Methods Absolute dose calibration was carried with thimble ionization chamber on the linear accelerator.so as to make sure 1 MU=1 cGy at the depth of maximum dose(dmax).A MatriXX was put into a Mutlicube phantom,and the ionization chamber matrix was calibrated with absolute dose.In order to determine a correction factor CF as a function of gantry angle θ.open beam fields of 10 cm×10 cm size were irradiated for gantry angles θ=0°-180°(every 5°)and every 1°for lateral angles θ in the range of 85°-95°.CF was defined as the ratio of the dose measured with ionization chamber and the dose from MatriXX.Results Relatively large discrepancies in response to posterior VS.anterior fields for MatriXX detectors(up to 10%)were found during the experiment and relatively large variability of response as a function of gantry angle.The pass rate of treatment plan in lateral beams was lower than that of other beams.The isodose distribution of corrected MatriXX matched well with the outcome from the treatment planning system. Conclusions The angular dose dependency of MatriXX must be considered when it is used to verify the treatment plan with original gantry angles.     

Dosimetric properties of a commercial PTW 60019 synthetic diamond detector in small photon fields

Objective To investigate the dosimetric properties of PTW 60019 synthetic diamond detector in small photon beams. Methods A PTW 60019 synthetic diamond detector was tested under 6 and 10 MV photon beams, respectively. Linearity with dose, dose rate dependence and off-axis ratio were measured and compared to those measured by an IBA SFD. Percentage depth doses were measured and compared to those measured by an IBA SFD and a PTW 31010 semiflex chamber. Total scatter factors were measured and compared to those measured by an IBA SFD and a PTW 31016 PinPoint chamber. Results The dose response of a PTW 60019 synthetic diamond detector showed a good linear behavior as a function of dose, with observed deviations below 0.2% over a dose range from 100 to 1 000 MU. The dose rate response was almost independent, with deviations below 0.2% in the dose rate range from 37 to 614 MU/min. For the fields of 20-100 mm in diameter, there were dose differences in percentage depth doses within 1% as compared to an IBA SFD and a PTW 31010 semiflex chamber. For the 10 mm diameter field, the differences were up to 5.8% in the build-up region. Off-axis ratios measurements showed a good agreement among the involved detectors (<1%). The higher differences appeared in the penumbra region. A good agreement was also found in terms of total scatter factor measurements for the related detectors. Conclusions The observed dosimetric properties of the PTW 60019 synthetic diamond detector indicate that it is a suitable candidate for small photon beam dosimetry.     

测量后装近距离放射治疗192Ir源参考空气比释动能方法学研究

目的 用NE2570剂量仪,2571指形电离室,测量 ¹⁹²Ir源空气比释动能支架,测量1m处 ¹⁹²Ir源参考空气比释动能。 方法将测量支架放在离墙、地面1m处,指形电离室插入有机玻璃测量支架夹具中,源中心距电离室中心的最佳距离是16cm, 源通过后装机的传输系统传输到施源器中,测量源参考空气比释动能。根据 ⁶⁰Co γ射线,250 kVΧ射线空气照射量刻度因子换算为空气比释动能刻度因子,再由内插公式计算 ¹⁹²Ir源空气比释动能刻度因子。对墙、地、空气、测量支架的散射校准因子,通过阴影屏蔽实验得到;对初始光子减弱校准因子;电离室壁产生的电子非均匀校准因子,均由IAEA的1079号报告(近距离放射治疗源的刻度)中查表得到。 结果在相同环境条件下,使用2种测量方法,指形电离室测量 ¹⁹²Ir源空气比释动能,经转换系数计算源外观活度为1.584×10¹¹Bq;井型电离室测量 ¹⁹²Ir源空气比释动能强度,经转换系数计算源外观活度为1.561×10¹¹ Bq,2个结果的相对偏差为 1.4%。结论指形电离室测量源空气比释动能,该物理量与源的结构、尺寸、壳材料、电离室形状、材质和尺寸无关,测量源空气比释动能与源的空气照射量比较,不确定度误差小。     

Rapid measurement of 210Po in seafood with large area grid ionization chamber α spectrometry

Objective To develop a rapid and reliable method for determination of ²¹⁰Po using large-area grid ionization chamber α spectrometry. Methods Samples were digested using a microwave digestion system. After preparation of sample source, the concentration of ²¹⁰Po in clam was detected by large-area grid ionization chamber (φ 25 cm). ²⁰⁹Po tracer was used to obtain the recovery. Results Large-area grid ionization chamber could achieve better counting and α spectrum resolution when the optimized thickness was 250 μg/cm². By spiking ²⁰⁹Po tracer in clam, the minimum detectable activity was 9.870×10^-4 Bq and the recovery of ²¹⁰Po was 98%. Conclusions Compared with the traditional method, the developed method can avoid separation process, using less quantity of sample (0.2-0.5 g dry) and simplify the measurement process. This method may be has broad application prospects.     

人的认知可靠性模型在高剂量率后装机卡源应急响应中的应用研究

目的 研究高剂量率(HDR)后装治疗机卡源事件的应急响应操作中的人因可靠性,提出合理可行的安全对策措施,从而提高HDR后装治机的应用安全.方法 采用人的认知可靠性(human cognition reliability,HCR)模型,对HDR后装机卡源应急响应中的10个操作失误类型进行分析,寻找失误原因及其危害,明确允许响应操作的时间窗.通过人员模拟、观摩和记录获取响应操作的执行时间,估算应急响应操作的人因失误概率.结果 获得了HDR后装机卡源响应中,操作人员执行的操作动作、相应的允许时间窗和执行时间以及各个动作的人因失误概率,失误概率为0.04～0.27.结论 基于HCR模型的HDR后装机卡源应急相应中操作人员的人因失误模型是可行的,从而为降低潜在照射事故的发生或减轻事故后果提供重要参考依据.

Abstract：

Objective To put forward reasonable and feasible recommendations aiming at enhancing the application safety of afterloading unit, through studying the human reliability in the emergency response against the source blockage of afterloading unit.Methods Based on the human cognition reliability model, ten operation errors during the emergency response against the source blockage of afterloading unit were analyzed and permissible time widow of emergency response operation were determined.The human error probability was calculated with the execution time of emergency response operation obtained through simulation, observation and recording.Results The operation action, relevant permissible time window and execution time were obtained with the corresponding human error probabilities in the range 0.04 - 0.27.Conclusions The human error model in emergency response against the source blockage of afterloading unit based on HCRmodel is feasible, and provides important reference basis to reduce the occurrence of potential exposure and mitigate the consequence of potential exposure.     

二极管半导体探测器(Diode)测量放射治疗患者剂量方法的研究

目的 研究用Diode探测器测量光子线束治疗中患者接受剂量的方法,验证治疗计划系统(TPS)计算剂量,并与Diode探测器测量剂量进行比较.方法 用60Coγ射线、6 MV X射线、水模体和固体模体,开展Diode探测器的重复性、剂量率响应、非线性剂量响应及刻度因子等实验.根据临床治疗需要,选择在不同条件下,研究剂量随机器角度、能量响应、源皮距、照射野、楔形角度、挡块和托盘因子等变化的影响,求出Diode探测器校准因子,用仿真人模体、Diode探测器、6 MV X线束,验证骨盆、头颈等部位剂量.再用Diode探测器测量6 MV X射线照射9例放疗患者的头颈、胸及腹等部位的剂量.结果 仿真人模体骨盆前面,左、右两侧(加楔形和不加楔形角度),以及头颈部左、右两侧(戴面具和不带面具)条件下,Diode测量值与TPS计算值的相对偏差均在±3%以内;放疗患者的头颈部两侧(戴面具)、胸部及腹部,Diode测量值与TPS计算值的相对偏差均在±5%以内.结论 用Diode探测器验证放疗患者剂量方法准确可靠,能快速获得数据.

Abstract：

Objective To explore the measurement method of the treatment dose of the patient with Diode for photon beam in radiotherapy,and to validate the treatment dose by comparing with the treatment planning system (TPS).Methods Experiments of the reproducibility,dose rate dependence,non-linearity dose response,and calibration factor in 60Co γ and 6 MV X beams were carried out with Diode on the surface of solid phantom and in water phantom.According to the needs of clinic treatment,different conditions were chosen to observe the dose changes with the angle of incidence,energy response,distance of source to skin,field size,wedge angle,block and tray using ionization chamber and water phantom.The Diode was placed on the surface of the solid phantom to obtain the correction factors.The doses of the chest,abdomen,and head and neek were verified with the Alderson phantom and Diode.Diode doses of the pelvis,head and neck at 14 points on the patient were measured.Results The Diode was irradiated at the points of the Alderson phantom,such as AP,RL and LL of the pelvis,with and without wedges,RL and LL junction of the neck and chin,with and without mask,the maximum relative deviation of doses was within ± 3% between Diode and TPS.The Diode was placed in different locations on the patient,including chest,abdomen and head and neck.The relative maximum deviation of doses was within ±5% between Diode and TPS.Conclusions The Diode method is reliable for measuring the exposure doses of the patient in radiotherapy.     

蒙特卡罗N粒子运输法计算与实际测量的60Co治疗机剂量分布比较

Objective To discuss the feasibility of Monte Carlo N-particle transport code(MCNP)simulated calculation.Methods The calculation in water phantom was contrasted with the practical measurements and the reported values using the percent depth dose(PDD)curve and normal peak scatter factor.Results There Was no significant difference between calculated and measured results in the 10 cm×10 cm field(t＝-0.41,P>0.05),however,there were significant differences in the 5 cm×5 cm field(t=7.2,P<0.05)and in the 12 cm×12 cm field(t=-4.6,P<0.05).There was no significant difierence between the calculated results and the reported values(t=-1.91,P>0.05).In the same radiation field,the PDD decreased as the depth increased,but increased as the size of the radiation field increased at the same depth.PDD and normal peak scatter factor were both important parameters for calculation of prescribed dose.Conclusions It is possible to establish a set of accurate and comprehensive percent depth doses and normal peak scatter factor parameters so as to provide the basis of clinical use, quality assurance and quality control for radiotherapy.     

蒙特卡罗N粒子运输法计算与实际测量的60 Co治疗机剂量分布比较

目的 探讨蒙特卡罗N粒子运输法(MCNP)模拟计算的可行性.方法 用百分深度剂量(PDD)分布及标准峰值散射因子(NPSP),比较水模体计算值和实际测量及报告值之间的差异.结果 在10 cm×10 cm射野时,测量值和计算值之间差异无统计学意义(t=-0.41,P>0.05),而在5 cm×5 cm及12 cm×12 cm时,测量值与计算值之间差异有统计学意义(t=7.2、-4.6,P<0.05).计算值和报告值之间符合良好,差异无统计学意义(t=-1.906,P>0.05).同一射野最大剂量点下百分深度剂量随深度增大而减少,同一深度处百分深度剂量随射野增大而增大;同一深度处射野中心轴上的剂量最高,向射野边缘剂量逐渐减少.结论 利用蒙特卡罗MCNP可以建立一组准确和全面的百分深度剂量及标准峰值散射因子参数,为放疗质量保证和质量控制提供依据.

Abstract：

Objective To discuss the feasibility of Monte Carlo N-particle transport code(MCNP)simulated calculation.Methods The calculation in water phantom was contrasted with the practical measurements and the reported values using the percent depth dose(PDD)curve and normal peak scatter factor.Results There Was no significant difference between calculated and measured results in the 10 cm×10 cm field(t＝-0.41,P>0.05),however,there were significant differences in the 5 cm×5 cm field(t=7.2,P<0.05)and in the 12 cm×12 cm field(t=-4.6,P<0.05).There was no significant difierence between the calculated results and the reported values(t=-1.91,P>0.05).In the same radiation field,the PDD decreased as the depth increased,but increased as the size of the radiation field increased at the same depth.PDD and normal peak scatter factor were both important parameters for calculation of prescribed dose.Conclusions It is possible to establish a set of accurate and comprehensive percent depth doses and normal peak scatter factor parameters so as to provide the basis of clinical use, quality assurance and quality control for radiotherapy.     

192Ir γ射线球形石墨空腔电离室室壁修正系数的模拟计算

目的 研究¹⁹²Ir放射源参考空气比释动能率基准电离室(NIM-Ir-SG-100型)的室壁修正系数。方法 利用蒙特卡罗程序计算经过放射源包壳和辐照器模型的光子光谱和电离室室壁修正系数,并对影响室壁修正系数结果的光子能量、壁厚和电离室内径进行了模拟。结果 经计算,球形石墨空腔电离室室壁修正系数模拟结果为1.037 7。控制单一变量,光子能量(0.3~1.3) MeV、壁厚(0.2~0.5) cm、电离室内径(0.5~15) cm对室壁修正系数结果的最大偏差分别为1.62%、3.30%、2.86%。结论 自制球形石墨空腔电离室性能良好,室壁修正系数k_wall值在合理范围内。室壁修正系数的完成为测量¹⁹²Ir放射源的参考空气比释动能率,建立计量基准完成重要的一步。     

Evaluation of Scatter Contribution and Distance Error by Iterative Methods for Strength Determination of HDR 192Ir Brachytherapy Source

High-dose rate (HDR) ¹⁹²Ir brachytherapy sources are commonly used for management of malignancies by brachytherapy applications. Measurement of source strength at the hospital is an important dosimetry requirement. The use of 0.6-cm³ cylindrical ionization chamber is one of the methods of measuring the source strength at the hospitals because this chamber is readily available for beam calibration and dosimetry. While using the cylindrical chamber for this purpose, it is also required to determine the positioning error of the ionization chamber, with respect to the source, commonly called a distance error (c). The contribution of scatter radiation (M_s) from floor, walls, ceiling, and other materials available in the treatment room also need to be determined accurately so that appropriate correction can be applied while calculating the source strength from the meter reading. Iterative methods of Newton-Raphson and least-squares were used in this work to determine scatter contribution in the experimentally observed meter reading (pC/s) of a cylindrical ionization chamber. Monte Carlo simulation was also used to cross verify the results of the least-squares method. The experimentally observed, least-squares calculated and Monte Carlo estimated values of meter readings from HDR ¹⁹²Ir brachytherapy source were in good agreement. Considering procedural simplicity, the method of least-squares is recommended for use at the hospitals to estimate values of f (constant of proportionality), c, and M_s required to determine the strength of HDR ¹⁹²Ir brachytherapy sources.     

Calibration coefficient of reference brachytherapy ionization chamber using analytical and Monte Carlo methods

A cylindrical graphite ionization chamber of sensitive volume 1002.4 cm³ was designed and fabricated at Bhabha Atomic Research Centre (BARC) for use as a reference dosimeter to measure the strength of high dose rate (HDR) ¹⁹²Ir brachytherapy sources. The air kerma calibration coefficient (N_K) of this ionization chamber was estimated analytically using Burlin general cavity theory and by the Monte Carlo method. In the analytical method, calibration coefficients were calculated for each spectral line of an HDR ¹⁹²Ir source and the weighted mean was taken as N_K. In the Monte Carlo method, the geometry of the measurement setup and physics related input data of the HDR ¹⁹²Ir source and the surrounding material were simulated using the Monte Carlo N-particle code. The total photon energy fluence was used to arrive at the reference air kerma rate (RAKR) using mass energy absorption coefficients. The energy deposition rates were used to simulate the value of charge rate in the ionization chamber and N_K was determined. The Monte Carlo calculated N_K agreed within 1.77 % of that obtained using the analytical method. The experimentally determined RAKR of HDR ¹⁹²Ir sources, using this reference ionization chamber by applying the analytically estimated N_K, was found to be in agreement with the vendor quoted RAKR within 1.43%.     

Study of scattered radiation for in-air calibration by a multiple-distance method using ionization chambers and an HDR 192Ir brachytherapy source

The aim of this study is to estimate the room-scatter correction when measuring air kerma rate of an HDR 192Ir brachytherapy source by in-air calibration. The variation in scattered radiation due to the specially designed jig and from the room walls was also studied. Two therapy ion chambers of volume 0.1 cm3 and 0.6 cm3 were used in the present study. Air kerma was measured by placing the source at several distances between 10 cm and 20 cm from the chamber. The scatter radiation was determined by superimposing the theoretically derived model curve of known scatter (based on the inverse square law) over the plot of measured air kerma strength values. The scatter radiation was estimated in terms of percentage of the primary radiation at 10 cm measurement distance. The scatter estimated by the 0.6 cm3 chamber at two positions was 0.33% and 0.59%, respectively. Similarly the scatter estimated at two other positions by the 0.1 cm3 chamber was 0.58% and 1.11%. This variation in scatter with position as well as with the chamber was due to the varying scatter contribution from components of the measurement set-up. The scatter radiation becomes constant at a distance greater than 100 cm from the walls of the room. We conclude that a fixed chamber with changing source positions should be used in multiple-distance measurement of air kerma rate when using a measurement jig.     

Consistency of vendor-specified activity values for 192Ir brachytherapy sources

A long-term comparison was done between the manufacturer-stated ¹⁹²Ir activity and the measured ¹⁹²Ir activities determined with a well-type ionization chamber. Sources for a Nucletron Micro Selectron high-dose-rate (HDR) unit were used for this purpose. The radioactive sources reference activities were determined using a PTW well-type ionization chamber traceable to the National Institute of Standards and Technology Primary Calibration Laboratory. The measurements were taken in a period of 56 months with 17 different radioactive sources. The manufacturer stated activities were taken from the source calibration certificate provided by the manufacturer. These values were compared with the measured activities. The results have shown that both the percentage deviation of the monthly control measurements with the well-type chamber and the ratio between the measured activities to the manufacturer-stated value lie within ± 2.5%. These results were compared with similar published data and with uncertainty level (3% of the mean and 5% maximum deviation from mean) for brachytherapy sources calibration recommended by the AAPM. It was concluded that a threshold level of ±2.5% can be used as a suitable quality assurance indicator to spot problems in our department. The typical ±5% uncertainty as provided by the manufacturers may be tightened to ±3% to be more in line with published AAPM reports.     

河南省核查放射治疗参考与非参考条件下剂量学参数方法验证

目的 研究用热释光剂量计（TLD）方法核查放射治疗参考条件和非参考条件下剂量学参数的可靠性验证。方法 在参考条件和非参考条件下,用建立的TLD方法,核查10条6 MV光子线束剂量随照射野大小和45°楔形板等变化,4条9 MeV电子线束轴向最大剂量点处等剂量学参数,TLD估算结果与剂量仪测量结果进行对比。结果 6 MV光子线束TLD估算结果与指形电离室测量结果的平均相对偏差为4.7%,按照IAEA要求允许偏差不超过±7%;9 MeV电子线束TLD估算结果与平行板电离室测量结果平均相对偏差为2.4%,均未超过IAEA允许偏差要求（±5%）。结论 用TLD核查参考条件和非参考条件下放射治疗剂量学参数方法可靠,简单易行。     

Calibration of a Microselectron HDR iridium 192 source

A method for the calibration of the output, in terms of an air kerma rate, of the high activity miniature iridium 192 sources used in the Microselectron HDR afterloading unit is described. An air kerma rate is measured using a calibrated thimble chamber in an "in-air" calibration jig. The results are compared with an air kerma rate derived from the manufacturer's test certificate. In some cases, the ionization chamber measurements have been followed by a further calibration check using thermoluminescent dosimetry. Other checks carried out when a new source is received are also briefly described.     

河南省医用加速器多叶光栅小野输出因子验证测量方法研究

目的 调查放射治疗计划系统(TPS)计算的多叶光栅(MLC)小野输出因子,研究用0.015 cc电离室验证小野输出因子的测量方法。方法 在河南省选择8台可开展调强放射治疗的医用加速器,调查TPS计算的小野输出因子并与国际原子能机构(IAEA)推荐的出版值进行比。如果2 cm×2 cm照射野相对偏差超出IAEA要求的±3%,3 cm×3 cm、4 cm×4 cm、6 cm×6 cm照射野相对偏差超出IAEA要求的±2%,则用0.015 cc电离室和Unidos剂量仪进行测量验证。结果8台医用加速器的TPS计算小野输出因子与出版值比较,5台相对偏差符合IAEA要求,占调查总台数的62.5%,3台相对偏差超过IAEA要求,占调查总台数的37.5%。用针尖电离室测量验证,3台测量结果均符合IAEA要求。结论 河南省部分医用加速器TPS计算的MLC小野输出因子,需要现场实施小电离室测量修正,测量值作为制定放射治疗计划的依据。