Monte Carlo Simulation of a Segmented Detector for Low-Energy Electron Antineutrinos

Detection of low-energy electron antineutrinos is of importance for several purposes, such as ex-vessel reactor monitoring, neutrino oscillation studies, etc. The inverse beta decay (IBD) is the interaction that is responsible for detection mechanism in (organic) plastic scintillation detectors. Here, a detailed study will be presented dealing with the radiation and optical transport simulation of a typical segmented antineutrino detector withMonte Carlo method using MCNPX and FLUKA codes. This study shows different aspects of the detector, benefiting from inherent capabilities of the Monte Carlo simulation codes.     

Simulation of the response functions of an extended range neutron multisphere spectrometer using FLUKA

In this paper, the distribution of radiation field in the CSNS spectrometer hall at Dongguan, China, was simulated by the FLUKA program. The results show that the radiation field of the high energy proton accelerator is dominated by neutron radiation, with a broad range of neutron energies, spanning about eleven orders of magnitude.Simulation and calculation of the response functions of four Bonner spheres with a simplified model is done with FLUKA and MCNPX codes respectively, proving the feasibility of the FLUKA program for this application and the correctness of the calculation method. Using the actual model, we simulate and calculate the energy response functions of Bonner sphere detectors with polyethylene layers of different diameters, including detectors with lead layers, using the FLUKA code. Based on the simulation results, we select eleven detectors as the basic structure for an Extended Range Neutron Multisphere Spectrometer(ERNMS).     

高能质子在散裂靶中的能量沉积计算与实验验证

高能质子在散裂靶中的能量沉积是散裂靶中子学研究的重要内容之一,准确掌握高能质子在散裂靶中引起的能量沉积分布与瞬态变化是开展散裂靶热工流体设计的重要前提.本文采用MCNPX,PHITS与FLUKA三种蒙特卡罗模拟程序,计算并比较了高能质子入射重金属铅靶、钨靶的能量沉积分布及不同粒子对总能量沉积的占比贡献;针对高能质子入射金属钨靶的能量沉积实验数据空白,采用热释光探测器阵列测量了250 MeV质子束入射厚钨靶的能量沉积分布,实验结果表明蒙特卡罗模拟程序在散裂靶中能量沉积的计算结果具有较高的可靠性.     

FLUKA Monte Carlo simulation code as used for radiation studies in the Alice experiment

The main features of the FLUKA Monte Carlo code, which can deal with transport and interaction of electromagnetic and hadronic particles, are summarized. The physical models embedded in FLUKA are described. Application of the code for the radiation background calculations. Especially, the origin and composition of the intense radiation field to be expected in parts of the ALICE detector for the coming multi-TeV LHC collider is described. It is important to evaluate the risk of radiation damage in detectors and electronics equipment. The text was submitted by the author in English.     

Coupled neutron transport for HZETRN

Exposure estimates inside space vehicles, surface habitats, and high altitude aircrafts exposed to space radiation are highly influenced by secondary neutron production. The deterministic transport code HZETRN has been identified as a reliable and efficient tool for such studies, but improvements to the underlying transport models and numerical methods are still necessary. In this paper, the forward–backward (FB) and directionally coupled forward–backward (DC) neutron transport models are derived, numerical methods for the FB model are reviewed, and a computationally efficient numerical solution is presented for the DC model. Both models are compared to the Monte Carlo codes HETC-HEDS, FLUKA, and MCNPX, and the DC model is shown to agree closely with the Monte Carlo results. Finally, it is found in the development of either model that the decoupling of low energy neutrons from the light ion transport procedure adversely affects low energy light ion fluence spectra and exposure quantities. A first order correction is presented to resolve the problem, and it is shown to be both accurate and efficient.     

Simulation of residual activity in steel and copper targets induced by 950 MeV/nucleon uranium ions

Radioactive nuclides will be produced in structures and surrounding materials of the relativistic heavy ion collider NICA. Predicting radioactivity in the materials, air, cooling water, and ground is an important part of the technical project. Some Monte Carlo transport codes (FLUKA, GEANT4, SHIELD) can simulate the production of radionuclides induced by heavy ions. The preliminary verification of MC codes with experimental data is necessary before using them for radiation protection purposes. In the present work, comparisons of the experiment and GEANT4 and SHIELD simulations of induced activity in thick stainless steel and copper targets irradiated with 950 MeV/nucleon uranium ions are presented.     

BEPCⅡ-LINAC试验束第二靶室混合辐射环境模拟

 为提供探测器或样品辐照实验与靶物质选择所需的辐射环境基本物理参数,利用蒙特卡罗模拟软件FLUKA对BEPCⅡ-LINAC试验束E2线上的第二靶室混合辐射环境进行了模拟计算,得到了以靶心为圆心,半径为1 m的球面上的各次级粒子的微分通量、角度微分截面、磁谱仪方位角上的双微分能谱、靶室内的剂量率分布。     

Charge distribution of the Kr ions resulting from the X-ray irradiation at 1.3 keV

The model of effective atomic potential and the Monte Carlo method are used to calculate the charge distribution of the Kr ions that are formed due to irradiation of neutral atoms by X-ray photons at an energy of 1.3 keV. The calculated results are in good agreement with the recent experimental data and can be used for development and maintenance of gas detectors that monitor the intensity of X-ray free-electron lasers.     

FLUKA程序在法拉第杯设计中的应用

法拉第杯是加速器束流强度绝对测量装置,其收集效率对于法拉第杯的设计至关重要。应用蒙特卡罗软件FLUKA对北京正负电子对撞机直线加速器分析磁铁AM2处的法拉第杯进行模拟设计。给出了法拉第杯不同部位对收集效率的影响曲线,并给出了入射电子在法拉第杯中的能量沉积分布与带电粒子分布图,最终得到了优化的法拉第杯尺寸,使得对入射电子的收集效率达到99.73%。     

低能电子在固体表面背散射系数的直接Monte Carlo方法模拟

应用单次碰撞的直接Monte Carlo方法计算能量范围从100 eV~10 keV的电子在固体Al,Si,Au表面的背散射系数,其中低能电子在固体中的弹性散射和非弹性散射截面分别应用Mott散射截面和Born近似下的广义振子强度计算模型得到.通过与压缩历史Monte Carlo方法的模拟计算结果及实验值的比较,结果表明,对于100 eV~10 keV范围的低能区电子,采用直接方法计算得到的电子背散射系数与实验值符合较好,直接方法比压缩历史方法更适合于能量在10 keV以下的电子输运计算.     

The microdosimetric one-hit detector model for calculating the response of solid state detectors

The microdosimetric one-hit detector model has been developed and applied to calculate the dose response, energy response and relative efficiency of thermoluminescent LiF:Mg,Cu,P and CaF₂:Tm detectors, and of the free-radical alanine dosimeter, after their exposure to radiation of different quality. The one-hit detector is described by two model parameters: the target diameter, d and the saturation parameter, α. Combining these parameters with microdosimetric distributions in nanometer-size targets calculated using Monte Carlo track structure codes TRION and MOCA-14, it was possible to describe and predict a great variety of experimental data for photon, X-ray, beta-electron, proton, alpha-particles and heavy ion irradiation. Within the framework of this biophysical model of radiation action, some mechanistic insight into the physics of radiation action in solid state detectors can be obtained.     

Relativistic graphene ratchet on semidisk Galton board

Using extensive Monte Carlo simulations we study numerically and analytically a photogalvanic effect, or ratchet, of directed electron transport induced by a microwave radiation on a semidisk Galton board of antidots in graphene. A comparison between usual two-dimensional electron gas (2DEG) and electrons in graphene shows that ratchet currents are comparable at very low temperatures. However, a large mean free path in graphene should allow to have a strong ratchet transport at room temperatures. Also in graphene the ratchet transport emerges even for unpolarized radiation. These properties open promising possibilities for room temperature graphene based sensitive photogalvanic detectors of microwave and terahertz radiation.     

120~430 MeV/u 碳离子的微剂量学特性研究(英文)

单粒子微剂量谱在放射治疗中是一个极其重要的参数,它可以用来评估辐射场的生物学效应。利用蒙特卡洛程序FLUKA模拟计算了由碳离子产生的混合辐射场能量沉积的微观模式。从已公开发表的文献中选取了实验测量300 MeV/u 碳离子的线能能谱,并与相同物理条件下模拟计算得到的线能能谱相比较,结果吻合得很好。此外,还计算了120~430 MeV/u 的碳离子的剂量平均线能能谱、频率平均线能和剂量平均线能。所得到的频率平均线能值为185~ 28.3 keV/m而剂量平均线能值则为272~ 64.1 keV/m。本文的结果对于制定碳离子放射治疗的治疗计划有着重要的意义.Microdosimetric single event spectrum is a significant parameter in radiotherapy, which can be used to evaluate the radiation biological effect. In this paper, microscopic patterns of energy deposition are simulated with Monte Carlo code FLUKA at mixed radiation fields during carbon ions therapy. The results are compared with experimental measured results at 300 MeV/u carbon ion and good agreement has been found. Meanwhile, dose-weighted lineal energy spectra, frequency averaged lineal energy values and dose averaged lineal energy values of carbon ion with energy from 120 to 430 MeV/u were calculated,too. The frequency averaged lineal energy values are from 185 to 28.3 keV/m while the dose averaged lineal energy values are from 272 to 64.1 keV/m. These studies are useful for treatment plan in carbon ion radiotherapy.     

利用GEANT4和FLUKA研究质子诱发散裂反应出射中子双微分截面

在中高能质子诱发散裂反应相关核工程设计中,可靠的蒙特卡罗模拟程序结合核反应理论模型具有较好的理论指导意义。本工作中,利用GEANT4耦合INCL4和ABLA理论模型以及FLUKA耦合PEANUT模型模拟计算了几百MeV至几个GeV质子轰击Be,Al,Fe,W,U等靶后30°,60°,120°,150°出射角产生的散裂中子双微分截面,并与现有实验数据进行了比较。结果发现,FLUKA和GEANT4模拟计算较好地再现了Al,Fe,W,U等靶实验测量数据。然而,模拟结果明显低估了Be靶出射中子能量小于10 MeV能区的实验数据。For the design of nuclear engineering related with medium-high energy proton induced spallation reaction,the reliable Monte Carlo simulation codes coupled with nuclear reaction models have a good theoretical guidance.In this work,the production spallation neutron double differential cross sections at 30°,60°,120°,150°emission angle for Be,Al,Fe,W,U target materials at incident proton energies between several hundred MeV and GeV are theoretically calculated by using the GEANT4 coupled INCL4 and ABLA,and the FLUKA coupled PEANUT.The calculated results were compared with the available experimental data.It is found that the GEANT4 and FLUKA calculations well reproduced the experimental measurement of Al,Fe,W,U target materials.However,calculations obviously underestimated the emission neutrons of Be target for lower than 10 MeV energy range.     

Monte Carlo simulations of the production of neutrons at iThemba LABS

FLUKA Monte Carlo radiation transport code has been used to simulate neutron fluence spectrum at iThemba LABS neutron beam facility. Neutron beams with energy up to 200 MeV can be produced using different targets such as ⁷Li, ⁹Be and ¹²C bombarded with monoenergetic protons from the Separated-Sector Cyclotron. Simulated results at 66 MeV were compared with measured data. Different neutron emission angles with respect to the beam axis as well as the neutron background at different positions have been investigated.     

Simulation of induced radioactivity for a heavy ion medical machine

The radioactivity induced by carbon ions of the Heavy Ion Medical Machine (HIMM) was studied to asses its radiation protection and environmental impact. Radionuclides in the accelerator component, and in the cooling water and air at the target area, which are induced from primary beam and secondary particles, are simulated by FLUKA Monte Carlo code. It is found that radioactivity in the cooling water and air is not very important at the required beam intensity and energy that is needed for treatment, while radionuclides in the accelerator component may cause some problems for maintenance work and, therefore, a suitable cooling time is needed after the machine is shut down.     

A model for distinguishing between static and dynamic exposure of personal thermoluminescence dosimeters

To distinguish between static and dynamic (normal) exposure of personal TL dosimeters, a model of radiation deposition and of TL light transport in the TLD dosimeter is proposed. The RADOS dosimeter badge using MCP-N (LiF:Mg,Cu,P) TL detectors with standard filters replaced by special Pb and Cu filters with a pattern of holes or inserts was modelled. The photon radiation transport in the dosimeter and energy deposition in the TL detector were simulated by the Penelope Monte Carlo transport code. The model of TL light transport within the TL pellet takes into account the distribution of energy deposition in the TL detector, light self-absorption in the detector and reflection of TL light of the heating planchet. The shape and hole pattern of the filters were optimized with respect to best distinction between static and dynamic exposures. The results of calculations were verified experimentally by exposing RADOS badges with modified filters to beams of low energy X-rays directed at various angles.     

Overview of novel techniques for radiation protection and dosimetry

Generally, the main approaches for assessing the radiation protection (RP) quantities in neutron fields are: i) the use of an instrument with a response to the protection quantity quasi-independent of energy; ii) neutron spectrometry; iii) microdosimetry.The techniques based on the first approach include rem-meters, superheated emulsions and the electronic personal dosemeters. Passive rem-meters have recently been developed for assessing the ambient dose equivalent in pulsed neutron fields around particle accelerators for hadrontherapy and research. Most of these instruments are characterised by a response extended to high-energies (up to a few GeV). An example is given by the GSI-ball, which employs a pair of LiF TLDs as a thermal neutron detector. It is likely that passive instruments will play a fundamental role also for monitoring the neutron fields generated by ultra-high intensity lasers, where the duration of a single pulse is of the order of hundreds femtoseconds.Arrays of tissue-equivalent proportional counters (TEPCs) of a millimetric/sub-millimetric physical size have been developed both for assessing the quality of therapeutic radiation beams and for estimating the RP quantities in low-intensity fields, which may limit the use of conventional microdosemeters. Very satisfactory results were obtained with GEM-based TEPCs and gas microstrip detectors (GMDs). Moreover, mini-TEPCs have been constructed and tested for measuring the quality of hadrontherapy beams (BNCT included). Silicon microdosemeters have also been demonstrated to be very promising for characterizing proton and ion beams for radiation therapy and for estimating the occurrence of single event effects in space applications.     

基于VENUS-III国际基准模型的JMCT程序验证

基于自主研制的三维中子-光子耦合输运蒙特卡罗通用程序JMCT（J Monte Carlo Transport Code）,采用连续点截面,对国际基准屏蔽VENUS-III模型开展精细建模和中子输运临界及屏蔽计算.临界计算得到系统k_eff、重要区域的通量及能谱.结果表明,JMCT和MCNP程序的重要区域体通量计数吻合较好,偏差均在1%以内.深穿透屏蔽计算采用外源模式,点探测器计数,JMCT计算值与实验测量值偏差在15%以内,满足屏蔽设计对误差的要求.初步验证了JMCT程序临界及屏蔽计算的可用性.     

中国锦屏地下实验室缪子辐射环境蒙特卡罗方法模拟

用蒙特卡罗方法对中国锦屏地下实验室（CJPL）的缪子辐射本底进行了模拟。在对宇宙线缪子进行模拟时,依据海平面缪子流强Gaisser公式建立模型,并利用MUSIC程序,模拟了CJPL实验室的剩余缪子归一化能谱,进一步利用FLUKA程序模拟得到了缪致光子、中子的产额和平均能量。结果表明:剩余缪子的平均能量369 GeV,通量3.1710-6 m-2s-1,次级光子总的注量率约1.5710-4 m-2s-1,次级中子总的注量率约8.3710-7 m-2s-1。通过与世界上其他地下实验室本底水平的对比,表明CJPL的缪子辐射环境低于世界上大多数地下实验室。