基于蒙特卡罗数学模型评价不同螺距冠状动脉CCTA受检者辐射剂量的特点与验证

收集61例采用双源CT Flash大螺距冠状动脉CCTA (Coronary Computed Tomography Angiography,CCTA)受检者资料,按WHO亚洲人体质量指数(BMI )标准将研究对象分为三组:正常组(12例)、超重组(41例)和肥胖组(8例),应用蒙特卡罗(Monte Carlo)数学模型软件计算三组受检者大螺距与常规螺距行CCTA的器官剂量,比较两种螺距CCTA时受检者的器官剂量分布特点及两种螺距CCTA的有效剂量变化幅度,并与大螺距模式下CT设备直接读取法所得有效剂量值进行比较。结果表明,用蒙特卡罗软件计算的双源CT大螺距CCTA受检者的器官剂量比常规螺距技术的剂量降低约70%,其中心脏、胸腺的器官剂量下降最为明显,降幅最大约80%;三组CCTA受检者大螺距较常规螺距的有效剂量(E)均降低明显(p<0.05),正常组使用大螺距技术后有效剂量E降幅最为明显;大螺距模式下数学模型软件模拟有效剂量E与CT设备所测有效剂量E间的偏差度小于50%。说明Monte Carlo数学模型软件可用于检查前预估或回顾性分析CCTA扫描时受检者的器官剂量与有效剂量的分布情况,并预判CCTA大螺距模式对受检者的胸部器官剂量和有效剂量,从而达到了降低辐射剂量的目的,尤其对BMI较小的受检者(如儿童)控制辐射风险更具意义。对开展低剂量CT技术具有一定实际意义。     

Gate/Geant4-based Monte Carlo simulation for calculation of dose distribution of 400 MeV/u carbon ion beam and fragments in water

The applications of carbon ion beam in tumor therapy have attracted more attention in recent years.Monte Carlo simulation is an important approach to obtain accurate radiotherapy parameters. In this work, a400 Me V/u carbon ion beam incident on water phantom was simulated with Gate/Geant4 tools. In methods, the authors set up a carbon ion beam source according to the experiment parameters of Haettner, defined the geometries and materials, set up the physics processes, and designed the means of information collection. In results,the authors obtained the longitudinal dose distribution, the lateral dose distribution, and the relative uncertainty of dose. The dose contributions of all kinds of fragments were calculated detailedly and compared with the Francis results. This work is helpful for people's understanding of the dose distributions produced by carbon ion beam and fragments in water. The simulation method is also significative for radiotherapy treatment planning of carbon ion beam, and it is easy to extend. For obtaining a special result, we may change the particle energy, particle type,target material, target geometry, physics process, detector,etc.     

Development of an effective dose calculation method for the downstairs room of a linac facility

ABSTRACT

An effective dose calculation method is important in the design of efficient shields in radiation facilities. Some analytical methods have been shown to provide a simple and quick design analysis; however, no suitable method exists that can be applied to a room located directly under an X-ray irradiation room. We propose a new analytical method that uses the multiple reflection ratio predetermined by a Monte Carlo simulation and the differential dose albedo given by the Chilton–Huddleston semi-empirical equation. Our method is verified by comparison with the Monte Carlo simulation, performed for the case of an electron linac facility with an accelerated energy of 10 MeV, where the shielding floor has a thickness of 1.6–2.0 m and the downstairs room has a height of 0.5–1.5 m. The difference between the effective X-ray doses in the downstairs room calculated via the proposed analytical method and the Monte Carlo simulation is less than 25% when the horizontal distance from the X-ray beam to the evaluation point exceeds 3 m and the evaluation point is set at half of the height of the room. The new analytical method can be efficiently and accurately applied to the calculation of the effective dose.     

Neutron and photon doses in high energy radiotherapy facilities and evaluation of shielding performance by Monte Carlo method

Medical accelerators operating above 10 MV are a source of undesirable neutron radiations which contaminate the therapeutic photon beam. These photoneutrons can also generate secondary gamma rays which increases undesirable dose to the patient body and to personnel and general public. In this study, the Monte Carlo N-Particle MCNP5 code has been used to model the radiotherapy room of a medical linear accelerator operating at 18 MV and to calculate the neutron and the secondary gamma ray energy spectra and the dose equivalents at various points inside the treatment room and along the maze. To validate our Monte Carlo simulation we compared our results with those evaluated by the recommended analytical methods of IAEA Report No. 47, and with experimental and simulated values published in the literature. After validation, the Monte Carlo simulation has been used to evaluate the shielding performance of the radiotherapy room. The obtained results showed that the use of paraffin wax containing boron carbide, in the lining of the radiotherapy room walls, presents enough effectiveness to reduce both neutron and gamma ray doses inside the treatment room and at the maze entrance. Such evaluation cannot be performed by the analytical methods since room material and wall surface lining are not taken into consideration.     

Simulation Experiment about the Effects of Core Heterogeneity on the Transient Pressure Behavior in the High-Energy Excursion of Fast Reactor

Gamma-ray dose distribution was measured in an actual ship to study applicability of point kernel method popularly applied to the calculation of γ-ray dose distribution in ships which have usually compartmentalized structures. Measured distribution was used to verify applicability of Monte Carlo method to the analysis of γ-ray dose distribution in the ship. Monte Carlo method was proved to be effective for analysis of r-ray dose distribution in the ship.

Monte Carlo analysis revealed that γ-rays scattered back from steel plates constructing ship hull increase their contribution to measured dose value as the distance between the dose measuring point and γ-rays sources increases. This contribution has not been taken into account in dose distribution calculations for ships by the point kernel method with the usual buildup factor.

Present study also disclosed that feasibility of applying Monte Carlo method to the analysis of γ-rays dose distribution in ships will be enhanced remarkably by utilizing the function adopted in the subroutine RELCOL in the Monte Carlo code MORSE-CG and by applying the source direction biasing technique to save machine time and to improve statistics of the calculated results.     

MatriXX二维电离室阵列剂量分布的角度响应

用Monte Carlo模拟、三维水箱和MatriXX测量的方法,获取机架角在0°–80°和280°–360°(0°)内的6 MVX射线的离轴比曲线,利用三种曲线分析MatriXX二维电离室阵列的角度响应。结果表明,在0°–60°和300°–360°(0°),三种方法得到的离轴比曲线一致性较好;在70°–80°和280°–290°,Monte Carlo计算和MatriXX测量的曲线及平面中心点剂量均存在明显差异。研究结果为多机架角度照射合成验证调强放疗计划的剂量分布提供依据。     

基于90Sr源β射线的外推电离室入射窗修正因子

为实现外推电离室对β辐射吸收剂量的准确测量,对影响外推电离室入射窗修正因子k_wi的主要量进行了研究。实验测量了外推电离室不同极间距和不同源 探距（源到外推电离室入射窗表面的距离）下的k_wi。研究结果表明,在源 探距不变的条件下,k_wi随电离室极间距的增大而减小;在电离室极间距为3 mm的条件下,k_wi随源-探距的增大而减小。利用蒙特卡罗模拟计算出不带展平过滤器、源 探距为30 cm、电离室极间距为3 mm时,k_wi为1.0845,与实验测量结果比较,其相对偏差为0.11%。因此,在给出k_wi的同时,应提供相应的源-探距和电离室极间距。     

高气压电离室能量响应的模拟计算

高气压电离室因其能量响应好而被广泛应用于环境γ本底测量。电离室外壳形状及材料的选择对其能量响应的影响非常大,本文采用蒙特卡罗方法对AGM-5型电离室的能量响应做了模拟计算,计算结果与实验刻度值吻合得比较好。     

高气压电离室能量响应的模拟计算

高气压电离室因其能量响应好而被广泛应用于环境γ本底测量。电离室外壳形状及材料的选择对其能量响应的影响非常大,本文采用蒙特卡罗方法对AGM-5型电离室的能量响应做了模拟计算,计算结果与实验刻度值吻合得比较好。     

在Logit-log直线回归中自动剔除“坏点”的一种方法

本文介绍一种在Logit-log直线回归中自动剔除“坏点”的方法、使用效果以及用蒙特卡罗法对该法与其他拟合方法的比较结果。     

含钚材料测量中的中子增殖校正和蒙特卡罗计算

运用蒙特卡罗方法计算了ＰｕＯ２标样的符合增殖校正因子。对含Ｐｕ量分别为２、１０、４０ｇ的３个标样，计算的校正响应接近常数，表明蒙特卡罗方法对ＰｕＯ２标样是有效的。将计算的符合响应与实验的符合响应相结合，得到了一条刻度曲线，利用这条刻度曲线分析了低类炉渣的一个样品，结果偏高５．３％。计算的校正响应，对金属样品，与标样相差６．７％；对部分氧化的样品如高类炉渣和零类炉渣，与标样的差异较大，蒙特卡罗方法在这种情况下的有效性有待进一步实验验证。     

放疗中二维平板电离室阵列所测剂量的空间映射研究

二维平板电离室阵列常用于临床放疗的剂量分布探测,其所测剂量实际对应的空间位置（即有效测量点或剂量-空间位置对应关系）是精确放疗中需研究的重要问题。本文采用蒙特卡罗方法研究了用于放疗剂量分布监测的二维平板电离室阵列的有效测量点位置及其随电离室的空腔直径、空腔厚度和射线能量等的变化规律。先用蒙特卡罗模拟得到水模体在MeV级光子束辐照下射野中心轴上的剂量曲线,再在相同条件下模拟获得二维平板电离室阵列测得的剂量曲线,然后通过相关性分析,得到有效测量点。结果表明,用于放疗的二维平板电离室阵列的有效测量点相对于前表面中心有一小于1 mm的偏移;该偏移量随电离室空腔厚度、射线能量的增加而增加,随电离室空腔直径的增加而减小。     

蒙特卡罗模拟在预测稀土尾渣辐射水平的应用

为了评估稀土尾渣的辐射水平,本文以典型的独居石选冶生产稀土后产生的含钍尾渣作为研究对象,应用蒙特卡罗模拟方法来计算桶装含钍尾渣周围的空气吸收剂量率。模拟计算结果与实测结果比较相对偏差均未超过20%,表明用蒙特卡罗模拟方法来预测稀土尾渣辐射水平是可行的。     

Hazard curve evaluation method development for a forest fire as an external hazard on nuclear power plants

A method to obtain a hazard curve of a forest fire was developed. The method has four steps: a logic tree formulation, a response surface evaluation, a Monte Carlo simulation, and an annual exceedance frequency calculation. The logic tree consists domains of “forest fire breakout and spread conditions”, “weather conditions”, “vegetation conditions”, and “forest fire simulation conditions.” Condition parameters of the logic boxes are static if stable during a forest fire or not sensitive to a forest fire intensity, and non-static parameters are variables whose frequency/probability is given based on existing databases or evaluations. Response surfaces of a reaction intensity and a fireline intensity were prepared by interpolating outputs from a number of forest fire propagation simulations by fire area simulator (FARSITE). The Monte Carlo simulation was performed where one sample represented a set of variable parameters of the logic boxes and a corresponding intensity was evaluated from the response surface. The hazard curve, i.e. an annual exceedance frequency of the intensity, was therefore calculated from the histogram of the Monte Carlo simulation outputs. The new method was applied to evaluate hazard curves of a reaction intensity and a fireline intensity for a typical location around a sodium-cooled fast reactor in Japan.     

Monte Carlo Simulation of Dosimetric Parameters for Hybrid PdI Source in Brachytherapy

According to dose calculation formula recommended by AAPM TG-43U1,dose rate constant of Model 6711 ¹²⁵I brachytherapy source was calculated by Monte Carlo method. The calculation results were in good agreement with TG-43U1. Then, dose rate constant,radial dose function and anisotropy function of new hybrid PdI source were calculated by Monte Carlo method．Empiric equations were obtained for radial dose function．     

Mechanical System Surveillance Test Interval Optimization

Abstract

In general, functional tests are required periodically to detect failures in standby equipment as a means of assuring their availability on demand. However, these functional tests may have an adverse impact on the system availability, because of their potential negative effects such as unavailability at the period of testing, increase of failure rate resulting from excessive wear due to testing. Therefore, in principle, there is an optimal test interval for each standby system. As it normally is difficult to determine analytically the optimal test interval for the real systems in the industry, we therefore introduce the Monte Carlo simulation method for this purpose. In this paper, a one-component system was chosen firstly to introduce the concept of test interval optimization as well as the feasibility of using Monte Carlo simulation. Secondly, a real system in the nuclear power plant. Standby-liquid-control system, was studied using Monte Carlo simulation technique. The promising results obtained confirm the concept and methodology used.     

Method for converting in-situ gamma ray spectra of a portable Ge detector to an incident photon flux energy distribution based on Monte Carlo simulation

A matrix stripping method for the conversion of in-situ gamma ray spectrum, obtained with portable Ge detector, to photon flux energy distribution is proposed. The detector response is fully described by its stripping matrix and full absorption efficiency curve. A charge collection efficiency function is introduced in the simulation to take into account the existence of a transition zone of increasing charge collection after the inactive Ge layer. Good agreement is obtained between simulated and experimental full absorption efficiencies. The characteristic stripping matrix is determined by Monte Carlo simulation for different incident photon energies using the Geant4 toolkit system. The photon flux energy distribution is deduced by stripping the measured spectrum of the partial absorption and cosmic ray events and then applying the full absorption efficiency curve. The stripping method is applied to a measured in-situ spectrum. The value of the absorbed dose rate in air deduced from the corresponding flux energy distribution agrees well with the value measured directly in-situ.     

Use of poly(methyl methacrylate) in radioactive waste management: II. Monte Carlo simulations

Radioactive waste is generated from the nuclear applications and it should properly be managed in a radioactive waste management system. Different methods are available for treatment and conditioning of radioactive waste. Polymers can be used in the radioactive waste management as an embedding matrix. Poly(methyl methacrylate (PMMA) is a possible candidate material that can be used in the low level radioactive waste management. In this study, based on total resistible dose for PMMA, maximum waste activity that can be embedded into a waste drum was found via Monte Carlo simulations. In addition, Monte Carlo simulations for radioactive waste embedded into above mentioned polymer was performed and the dose rate distribution in the polymer matrix was determined for the initial and different periods of 15.1, 30.2 and 302 years after embedding of waste. Changes of mechanical properties in the polymer embedded waste drum was simulated for PMMA embedded waste matrices based on experimental data.     

A Simple Calculation for Air-Scattered Gamma-Rays

A simple formula for air-scattered γ-rays is proposed. The proposed formula is derived using a single-scattering approximation, with exponential attenuation and buildup factor for scattered γ-ray energy. The results of calculation obtained with the formula are compared with those by Monte Carlo method, and by single-scattering calculation without exponential attenuation and buildup, for line beams of mono-energetic γ-rays emitted from a point source.

For higher energies, the air-scattered flux and dose rate given by this simple approximation agree fairly well with the Monte Carlo calculations at all beam angles and source-detector distances. The accuracy is within about 10%.

The flux and dose rate for γ-rays emitted isotropically from the point source have also been calculated, and are presented as a function of distance.     

Optimization of GEANT4 settings for Proton Pencil Beam Scanning simulations using GATE

This study reports the investigation of different GEANT4 settings for proton therapy applications in the context of Treatment Planning System comparisons. The GEANT4.9.2 release was used through the GATE platform. We focused on the Pencil Beam Scanning delivery technique, which allows for intensity modulated proton therapy applications. The most relevant options and parameters (range cut, step size, database binning) for the simulation that influence the dose deposition were investigated, in order to determine a robust, accurate and efficient simulation environment. In this perspective, simulations of depth-dose profiles and transverse profiles at different depths and energies between 100 and 230 MeV have been assessed against reference measurements in water and PMMA. These measurements were performed in Essen, Germany, with the IBA dedicated Pencil Beam Scanning system, using Bragg-peak chambers and radiochromic films. GEANT4 simulations were also compared to the PHITS.2.14 and MCNPX.2.5.0 Monte Carlo codes. Depth-dose simulations reached 0.3 mm range accuracy compared to NIST CSDA ranges, with a dose agreement of about 1% over a set of five different energies. The transverse profiles simulated using the different Monte Carlo codes showed discrepancies, with up to 15% difference in beam widening between GEANT4 and MCNPX in water. A 8% difference between the GEANT4 multiple scattering and single scattering algorithms was observed. The simulations showed the inability of reproducing the measured transverse dose spreading with depth in PMMA, corroborating the fact that GEANT4 underestimates the lateral dose spreading. GATE was found to be a very convenient simulation environment to perform this study. A reference physics-list and an optimized parameters-list have been proposed. Satisfactory agreement against depth-dose profiles measurements was obtained. The simulation of transverse profiles using different Monte Carlo codes showed significant deviations. This point is crucial for Pencil Beam Scanning delivery simulations and suggests that the GEANT4 multiple scattering algorithm should be revised.