Monte Carlo studies for irradiation process planning at the Portuguese gamma irradiation facility.

The paper describes a Monte Carlo study for planning the irradiation of test samples for microbiological validation of distinct products in the Portuguese Gamma Irradiation Facility. Three different irradiation geometries have been used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity in different products. Based on these results, irradiation planning of the product can be performed.     

Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code.

This paper describes a complete Monte Carlo study of the Tunisian gamma irradiation facility (CNSTN) using the GEANT4 CERN's code. The work focused on the optimization of the absorbed dose distribution inside the irradiation cell, with and without product. For this purpose, 32 different points at the middle plane of the source rack, 29 positions along Z axis and 7 critical points, were carried out using PMMA dosimeters. Then, to achieve a given bulk density, boxes loaded with "dummy" product were used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity within product.     

Dose distributions at extreme irradiation depths of gamma knife radiosurgery: EGS4 Monte Carlo calculations.

The accuracy of the dose planning system (Leksell GammaPlan), used in Gamma Knife (type B) radiosurgery at extreme irradiation depths, was verified using the Monte Carlo technique. EGS4 Monte Carlo calculations were employed to calculate the dose distribution along the x, y and z axes for an irradiation relatively shallow in a spherical bony cavity water phantom. Two different sizes of the collimator helmets, 8 and 18 mm, of the Leksell Gamma Knife Unit were studied. The results of GammaPlan showed good consistency with the Monte Carlo results. Furthermore, small dose enhancements were observed in the skull bone where accurate dose measurements are difficult due to the presence of the air-phantom interface. Therefore, the results of this project can promote confidence to all Gamma Knife centres in the world when using the Leksell GammaPlan.     

Monte Carlo simulation of neutron irradiation facility developed for accelerator based in vivo neutron activation measurements in human hand bones.

The neutron irradiation facility developed at the McMaster University 3 MV Van de Graaff accelerator was employed to assess in vivo elemental content of aluminum and manganese in human hands. These measurements were carried out to monitor the long-term exposure of these potentially toxic trace elements through hand bone levels. The dose equivalent delivered to a patient during irradiation procedure is the limiting factor for IVNAA measurements. This article describes a method to estimate the average radiation dose equivalent delivered to the patient's hand during irradiation. The computational method described in this work augments the dose measurements carried out earlier [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724]. This method employs the Monte Carlo simulation of hand irradiation facility using MCNP4B. Based on the estimated dose equivalents received by the patient hand, the proposed irradiation procedure for the IVNAA measurement of manganese in human hands [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724] with normal (1 ppm) and elevated manganese content can be carried out with a reasonably low dose of 31 mSv to the hand. Sixty-three percent of the total dose equivalent is delivered by non-useful fast group (> 10 keV); the filtration of this neutron group from the beam will further decrease the dose equivalent to the patient's hand.     

Application of the Monte Carlo method for the calibration of an in situ gamma spectrometer

A MCNP model was developed for the efficiency calibration of an in situ gamma ray spectrometry system based on a high purity germanium (HPGe) detector. The detector active crystal volume was adjusted semi-empirically against experimental measurements. Calculated full energy peak efficiency curves, over the photon energy range between 50 keV and 5 MeV, are presented for surface and slab source configurations. The effect of different collimator apertures and the contribution of different HPGe crystal regions in the detector response are also shown.     

Optimization of a measurement facility for radioactive waste free release by Monte Carlo simulation

A novel free release measurement facility (FRMF) was developed within the joint research project “Metrology for Radioactive Waste Management” of the European Metrology Research Programme. Before and during FRMF design and construction, Monte Carlo calculations with MCNPX and PENELOPE codes were used to optimize the thickness of the shielding, the dimensions of the container, and the shape of detector collimators. Validation of the numerical models of the FRMF detectors and the results of the optimization are discussed in the paper.     

Monte Carlo dose parameters of the BrachySeed model LS-1 I brachytherapy source

Using a modified EGS4 code and associated user code DOSCGC, the two-dimensional dose rate distribution in water and air-kerma strength are calculated for a BrachySeed (model LS-1) ¹²⁵I brachytherapy source, based on geometry and material data provided by the manufacturer. The AAPM TG-43 dose parameters derived from these results include the dose rate constant, the radial dose function, the anisotropy function, and the anisotropy factor and constant. The value of the dose rate constant so obtained is 0.932±0.003 cGy h⁻¹ U⁻¹. The source strength calculation excludes the contribution from titanium characteristic X-rays (4.5 and 4.9 keV) in the source in order to comply with a new primary calibration standard implemented by the National Institute of Standards and Technology in 1999. A sampling procedure for simulating silver characteristic X-ray production in the mixture material of the source core is developed in the EGS4 code. The calculated results reveal the good dose isotropy of the LS-1 source. The Monte Carlo dose parameters obtained are compared with measurements and calculations of other investigators.     

Monte Carlo validation of the Dorfman-Berbaum-Metz method using normalized pseudovalues and less data-based model simplification

RATIONALE AND OBJECTIVES: Two problems of the Dorfman-Berbaum-Metz (DBM) method for analyzing multireader receiver operating characteristic (ROC) studies are that it tends to be conservative and that it can produce AUC estimates outside the parameter space--ie, greater than one or less than zero. Recently it has been shown that the problem of AUC (or other accuracy) estimates outside the parameter space can be eliminated by using normalized pseudovalues, and it has been suggested that less data-based model simplification be used. Our purpose is to empirically investigate if these two modifications--normalized pseudovalues and less data-based model simplification--result in improved performance. MATERIALS AND METHODS: We examine the performance of the DBM procedure using the two proposed modifications for discrete and continuous ratings in a null simulation study comparing modalities with respect to the ROC area. The simulation study includes 144 different combinations of reader and case sample sizes, normal/abnormal case sample ratios, and variance components. The ROC area is estimated using parametric and nonparametric estimation. RESULTS: The DBM procedure with both modifications performs better than either the original DBM procedure or the DBM procedure with only one of the modifications. For parametric estimation with discrete rating data, use of both modifications resulted in the mean type I error (0.043) closest to the nominal .05 level and the smallest range (0.050) and standard deviation (0.0108) across the 144 type I error rates. CONCLUSIONS: We recommend that normalized pseudovalues and less data-based model simplification be used with the DBM procedure.     

Dose mapping of a 60Co irradiation facility using PENELOPE and MCNPX and its validation by chemical dosimetry.

The Monte Carlo simulation programs PENELOPE and MCNPX have been used for simulating the dose rate distribution in a (60)Co gamma irradiator. The simulated isodose curves obtained for each simulation code were validated comparing them to the dose measurements performed with a Fricke solution, which is a standard dosemeter widely used in radiation processing for calibration purposes. The agreement between the simulated values and the measurements indicates the effectiveness of both codes in performing the dose-mapping simulation for gamma irradiators.     

6711型125I种子源剂量学参量的蒙特卡罗模拟研究

目的 计算6711型125I种子源的剂量特性.方法 使用EGSnrc蒙特卡罗模拟程序对种子源的各向异性函数、径向剂量函数和剂量率常数进行计算,并给出了不同介质中的空间剂量率分布,将计算结果与美国医学物理师协会(AAPM)TG43-U1号报告中的推荐值和其他已发表的相关数据进行了比较.结果 各向异性函数与其他最新发表的数据符合较好;径向剂量函数与TG43-U1推荐值符合较好;剂量率常数为0.951 cGy·h-1·U-1,与TG43-U1推荐值在1.45%内吻合.结论 6711型125I种子源剂量场具有低剂量率,高梯度的特点;各向异性函数在近距离小角度处存在小突起的结构.     

Changes of the peripheral blood picture after combined neutron and gamma irradiation

Changes of the peripheral blood picture of rats irradiated with a single dose of 2 Gy of neutrons were followed in comparison with a group of rats irradiated with a single dose of 2 Gy of neutrons followed by continuous gamma irradiation (daily dose rate 0.574 Gy, total dose 6 Gy). The decisive factor for the organism damage was the single 2 Gy neutron dose. The subsequent continuous gamma irradiation retarded the reparation of the peripheral blood elements.     

Monte Carlo validation of the self-attenuation correction determination with the Cutshall transmission method in 210Pb measurements by gamma-spectrometry

The accuracy of estimation of the self-attenuation correction C_s with the Cutshall transmission method in ²¹⁰Pb measurements by gamma-spectrometry was assessed using the Monte Carlo method. The Cutshall method overestimates the correction for samples with linear attenuation coefficient at 46.5 keV higher than that of the standard and underestimates it in the opposite case. The highest bias was found for thick samples. C_s,Cuts/C_s ratio grows linearly with sample linear attenuation coefficient.     

~(125)Ⅰ植入治疗源的剂量学参数的Monte Carlo模拟

放射性粒子源125I已被广泛用于前列腺和眼睛的植入治疗中。本文采用EGS5蒙特卡罗代码计算了美国医用物理学协会（AAPM）TG-43U1报告中推荐的型号为6711125I近距治疗源（活性区长取0.28cm）的剂量学参数,如剂量率常数、径向剂量函数和各向异性函数。剂量率常数为0.959cGy/h/U,与TG-43U1推荐值和Dolan等已发表的值相差在2.0%以内 径向剂量函数数值与二者均符合较好 随着角度和距离的增加,各向异性函数值数值与二者的复合程度趋佳。并给出了实用性较强的径向剂量函数的拟合公式。     

γ刀照射三叉神经的剂量-效应关系研究

目的 探讨伽玛刀不同剂量照射大鼠三叉神经(感觉根)后对照射范围内三叉神经组织的损伤以及对周围临近脑干组织和脑桥的影响,为优化伽玛刀照射剂量提供理论依据。方法 选用成年雄性SD大鼠65只,分别以不同照射剂量(20、40、80、160 Gy)照射三叉神经,观察照射后1周、2周、4周大鼠行为学变化,取全脑组织进行HE、Nissl、MAPLC3B、53BP1、XRCC1染色观察细胞形态学和自噬以及DNA损伤和修复等变化。结果 所有剂量组照射大鼠均存活。20和40 Gy组均无行为学和病理学改变;80和160 Gy组均出现了照射部位毛发脱落;HE、Nissle、LC3B、53BP1及XRCC1染色发现,受照部位组织在80和160 Gy照射后,可见神经元细胞固缩、膨胀,神经元细胞发生自噬以及DNA损伤明显,160 Gy组DNA损伤明显加重。40 Gy照射后,神经元发生DNA损伤修复的程度较其他剂量增高。结论 伽玛刀照射三叉神经根对神经元有明显的剂量-效应关系。     

Calculation of angular distribution of 662 keV gamma rays by Monte Carlo method in copper medium

This paper presents results on the angular distribution of Compton scattering of 662 keV gamma photons in both forward and backward hemispheres in copper medium. The number of scattered events graph has been determined for scattered gamma photons in both the forward and backward hemispheres and theoretical saturation thicknesses have been obtained using these results. Furthermore, response function of a 51×51 mm NaI(Tl) detector at 60° angle with incoming photons scattered from a 10 mm thick copper layer has been determined using Monte Carlo method.     

瓦里安高剂量率铱源剂量学参数的蒙特卡罗模拟研究

目的 采用美国医学物理师学会（AAPM）和欧洲放射治疗和肿瘤学会（ESTRO）推荐的蒙特卡罗方法对瓦里安GammaMed Plus HDR ¹⁹²Ir源的剂量学参数进行模拟研究。方法 基于EGSnrc蒙特卡罗软件,建立该型号¹⁹²Ir源精确的计算模型。采用公式推导、双线性插值及单位转换等方法,分别得到了单位活度空气比释动能强度、剂量率常数、径向剂量函数以及各向异性函数,并将结果与文献报道数据进行分析比较。结果 研究得到的单位活度空气比释动能强度为9.781×10^-8 U/Bq,剂量率参数为1.113 cGy·h^-1·U^-1,与文献报道的相差在0.4%以内。本研究的径向剂量函数、各向异性函数与文献数据能较好吻合。结论 基于EGSnrc蒙特卡罗软件能对¹⁹²Ir源剂量学特性进行定量研究,这将为进一步研究后装剂量分布,精确评价临床放疗剂量提供理论依据。     

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.