252Cf裂变γ射线伴随飞行时间法刻度液体闪烁体中子探测效率

宏观检验实验是检验核数据正确性的重要实验方法之一。液体闪烁体中子探测器是中子核数据宏观检验实验中快中子能谱测量的主要探测器,其探测效率曲线的准确性关系到实验结果的精度。本文采用²⁵²Cf中子源的伴随γ射线和飞行时间法测得了液体闪烁体对2.0～10.0 MeV中子的相对探测效率曲线,同时利用飞行时间法和400 kV脉冲中子发生器的d-D反应中子源测得了2.9 MeV单能中子的绝对探测效率。将相对探测效率曲线归一到单能点的绝对效率,得到探测器在这一能区的绝对探测效率曲线。使用蒙特卡罗程序NEFF模拟相同参数的液体闪烁体探测器对10.0 MeV以下中子的探测效率曲线。最后将实验结果与模拟结果对比,结果表明实验得到的探测效率曲线合理、准确。     

井型HPGe探测器探测效率的MC模拟

采用MC方法对井型HPGe探测器全能峰探测效率进行虚拟刻度。通过改变点源在井中的位置,研究了其探测效率变化规律,并进行了实验验证;同时模拟计算了探测器对0.1~1Me V能量的探测效率。模拟与实验结果表明:137Cs放射源在井中不同位置的实验测量结果与模拟值最大相对误差6.8%,最小相对误差1.5%;探测效率随放射源离井底距离增加而减小,随入射射线能量增大而减小。     

HPGe探测器能量刻度及探测效率模拟

X光机绝对光子数的测量在X射线计量中有着十分重要的意义,对其进行测量时需先将探测器的能量—道址函数进行刻度。本文使用放射源对HPGe探测器进行能量刻度,得到其能量—道址函数且其线性相关系数R2=0.999 84。论文结合了CT成像技术,对探测器进行平行光束探测效率的MC模拟,使建模更精确。模拟结果显示,探测效率曲线在11.0 ke V处会出现吸收边,是因为Ge元素被激发产生Kα、Kβ特征X射线发生逃逸,未被记录下来形成逃逸峰所致,这与实际实验情况相符。     

MC模拟HPGe探测器探测效率

利用MCNP法对HPGe探测器探测效率进行了模拟研究。实验选用~(152)Eu、~(137)Cs和~(60)Co标准源对HPGe探测器的探测效率进行刻度,并对模拟值和实验值进行了比较讨论。结果表明:与Geant4模拟结果相比,MCNP对HPGe探测器的模拟探测效率更能与实际探测效率吻合。此实验结果可为高性能HPGe探测器的设计与研发提供参考。     

γ全吸收型探测装置探测效率的实验与模拟

为精确测量keV能区中子俘获反应截面,中国原子能科学研究院核数据重点实验室基于中国散裂中子源反角白光中子源建成了国内首套γ全吸收型BaF₂探测装置。为获得重要的实验参数装置对γ射线的探测效率曲线,对单个BaF₂探测器模块能谱的测量数据与模拟结果进行比较。结果表明,测量¹³⁷Cs和⁶⁰Co源得到的实验结果与MCNP和GEANT4的模拟结果吻合较好,验证了模拟计算得到的探测效率曲线的可靠性,可用于中子俘获反应截面的在线测量。     

海水就地γ谱测量最小探测活度影响因素研究

海水就地γ谱测量可实现海洋放射性环境的实时在线监测和预警。为了确保准确测量海水中低含量的放射性核素,利用实验和MC模拟研究了Na I(Tl)就地γ谱仪本底计数、测量时间和探测效率对最小探测活度的影响。结果表明:将γ谱仪放置在合适的测量深度可减小本底计数,从而降低最小探测活度;γ射线能量、探测器晶体类型及体积、封装材料类型及厚度也会对最小探测活度产生影响。研究结果可为海水就地γ谱仪的研发和改进提供重要参考依据。     

HPGe探测器对环状γ面源探测效率刻度研究

天然铀分解模拟装置中铀的相关反应率是研究混合堆包层设计宏观中子学的重要数据,采用活化法测量相应反应率的过程中必须对环状天然铀箔片的探测效率进行精确刻度。为了研究快速有效刻度HPGe探测器探测效率的方法,利用一系列标准伽马点源测量了轴线上6cm高度位置的点源探测效率曲线,在蒙特卡罗程序MCNP5中调整探测器内部结构参数,同时对HPGe探测器的探测效率进行模拟计算,在计算结果与实验结果能较好拟合的情况下推算探测器的死层厚度、冷指长度和半径等参数的实际尺寸。利用计算的尺寸模拟计算探测器对环状伽马源的探测效率,计算结果与实验结果在较宽能量区域(200~1 400 ke V)内在4%内符合。     

碳化硅与硅探测器辐射探测性能比较

碳化硅(SiC)材料因其禁带宽度大、晶体原子离位能高等物理特性,而被视为制作耐高温和抗辐射器件极具潜力的宽带隙半导体材料。本文采用Geant4模拟得到了30μm厚的SiC和Si材料对不同能量的电子、质子、α粒子以及X射线的响应,并对SiC和Si探测器器件的I-V特性和能谱测量结果进行了比较。仿真及试验结果证明,SiC粒子阻挡本领及X射线探测效率与Si探测器相当,SiC与Si探测器对带电粒子的能谱分辨率也没有明显差别。     

脉冲射线束探测技术

脉冲射线束探测是一个特殊的应用技术学科,作为核探测技术的一个分支,它应用于核试验、惯性约束聚变等强脉冲射线源诊断。本文将比较全面地评述脉冲射线束探测问题。分别就它的测量对象、测量系统、探测方法与探测器等方面进行原理性介绍和讨论。力求把国外新的技术发展包括在内,希望能引起同行的兴趣。     

350 kV高压X射线密度测井探测深度特性及影响

密度测井中使用可控X射线源替代¹³⁷Cs放射源已经成为新的趋势。X射线源强度受靶基上高压影响较大，当高压为350 kV时密度测量不确定度可以保持在0.01 g·cm^-3。为探究350 kV高压X射线密度测井仪器的探测深度特性及影响，利用蒙特卡罗方法研究了不同源距探测器在20%含水石灰岩地层中的探测深度；并且通过与¹³⁷Cs源密度测井仪探测特性的对比，分析了二者探测深度差异的原因。另外通过模拟分析了泥饼和地层对探测器的贡献度以及不同探测器的密度偏差，研究了井壁泥饼对密度测井响应的影响。研究结果表明：X射线密度测井仪的探测深度随着源距的增加而变大；与¹³⁷Cs源密度测井仪相比，X射线密度测井仪散射粒子主要集中于井壁1～3 cm处，从而造成二者探测深度差异；此外，泥饼和地层对不同源距探测器的贡献度不同，探测器密度偏差随着源距增加而减小。     

Recent Advances in X-Ray Detection Technology

A review is presented of recent developments in x-ray photon detectors and in the associated detector electronics. The first portion of the paper is devoted to a survey of the presently available physical inforrnation on the "intrinsic" resolution of silicon and germanium radiation detectors, proportional counters and NaI(Tl) scintillation crystals. Semiconductor detectors suitable for x-ray applications and low noise electronics are then analyzed in some detail. Discussions follow on scintillation detectors, proportional counters, and "external" photoelectric detectors. Recent spectral achievements and interesting applications are illustrated.     

“核-光转换”中子探测系统物理结构的模拟研究

"核-光转换"中子探测器是以惰性气体为介质将裂变碎片能量转换为光辐射的裂变室,拥有电离探测器所没有的优点:不需要供电电源;信号传输方式采用光导或光纤,而不是绝缘电缆;对伽马辐射极不灵敏;输出信号较大,可以避免在探测器附近使用前置放大器。根据"核-光转换"中子测量系统的特点,采用Geant4模拟了铀裂变靶厚度、惰性气体成分、腔体材料等对到达惰性气体的裂变碎片和可见光的影响,给出了NOC结构设计的最佳参数和中子能量响应。     

爆炸物检测中的模拟计算

为优化基于伴随α粒子技术的爆炸物检测系统中的γ探测器和数据分析软件,利用蒙特卡罗程序EGSnrc对γ探测器的探测效率和能量响应分别进行了模拟。NaI(Tl)、BGO等几种无机闪烁体γ探测器探测效率的模拟计算结果为探测器的优化选择提供依据;对碳、氧单质元素、硝酸氨、模拟炸药样品在14MeV中子作用下的特征γ射线,在Φ5″×8″NaI(Tl)探测器的能量响应模拟计算结果进行了分析,并与实验测量能量响应进行了比较。结果表明,模拟方法可靠,应用该方法可对其他的单质材料来进行响应计算以建立响应函数数据库。     

Maximum-likelihood principle for determining positions in neutronscintillation detectors

Pulse height division is generally used to determine a position channel for storing detection events in position-sensitive detectors (PSDs). An alternative method based on the maximum likelihood principle is discussed. This principle is modified in order that the storage of events can be done online. Analytic expressions for the spatial resolution are derived and evaluated. Both detection methods are simulated for linear PSDs. Results on uniformity, linearity, stability and spatial resolution are presented. The major specific advantage of the proposed method is an improved uniformity of the response along the entire detector     

Fluorination of UF4 in a mini-tapered fluidized bed and mathematical modeling

A mini-tapered fluidized bed reactor can be used for fluorination reaction of UF₄ to produce uranium hexafluoride. By adopting the mini-tapered bed the problems associated with fluidization in a cylindrical bed such as entrainment of particles and the limitation of operating velocity can be overcome, consequently the performance of the reactor can be enhanced. Simulation of the reactor was performed employing two-phase models, bubble phase with piston flow and emulsion phase with piston (D.P-P model) or perfectly mixed flow (D.P-M model). The voidage of the emulsion and bubble phases were estimated from the distribution two-phase structure hydrodynamic model. The model predictions have been compared with the results from a pilot-scale experiment. The D.P-P model gives good agreement between computed and empirical results. The effects of various parameters on the reactor performance are discussed using the model.     

Some Problems in High-Energy Particle Detection and Analysis

1. The kinematic analysis of high-energy events requires, in general, particle momentum measurements with an absolute error of ±50-100 MeV/c, independent of momentum. Corresponding errors are 0.05% at 100 GeV/c, less at higher momenta. To minimize the cost of magnetic deflection of high-energy particles, improvements in angular precision, hence, in particle location accuracy, are desirable. The present analysis indicates that improving location accuracy from ±1/3 mm to ±0.1 mm is both desirable and feasible. The usefulness of still higher precision must await data on detailed systems performance. 2. For complex events, it appears likely that vidicon digitization can compete favorably in cost, convenience, and flexibility with large wire-array systems. 3. Neutral particle detectors that furnish accurate data on the location and direction of neutral particles (gamma rays, neutral hadrons) are likely to be important.     

Optimization of moderator assembly for neutron flux measurement: experimental and theoretical approaches

A moderator of paraffin wax assembly has been demonstrated where its thickness can be optimized to thermalize fast neutrons. The assembly is used for measuring fast neutron flux of a neutron probe at different neutron energies, using BF03(U10and 200) and3He(U0.500)neutron detectors. The paraffin wax thickness was optimized at 6 cm for the neutron probe which contains an Am–Be neutron source. The experimental data are compared with Monte Carlo simulation results using MCNP5 version 1.4. Neutron flux comparison and neutron activation techniques are used for measuring neutron flux of the neutron probe to validate the optimum paraffin moderator thickness in the assembly. The neutron fluxes are measured at(1.17 ± 0.09) 9 105 and(1.19 ± 0.1) 9 105n/s, being in agreement with the simulated values. The moderator assembly can easily be utilized for essential requirements of neutron flux measurements.     

15MV医用电子直线加速器光核中子剂量分布的MC模拟及测量

医用电子直线加速器产生的X射线已广泛应用于放射治疗过程,X射线与机头中的高Z物质(铅、钨、铜和铁)发生(γ,n),(γ,2n)反应产生一定量的中子,引起与治疗无关的中子剂量。本文对工作在15MV能量档的Prim μs-M型医用电子直线加速器在标准照射野10cm×10cm内治疗平面的光中子剂量分布,进行了Monte-Carlo模拟,并使用CR39固体核径迹探测器和中子气泡探测器(NBD)进行了实验测量。研究发现,测量与模拟的中子剂量之间最大偏差约±30%,其最主要的原因是由于"加速器产生的光核中子与物质发生非弹性散射反应"而逐步降低能量,产生了低于上述两种探测器阈能(100keV)的中子,使测量值比模拟值偏低。研究结果为X射线放射治疗中减低污染中子剂量的优化设计提供了基础数据。     

A Stochastic Operator Method of Calculating the Time Interval Distributions in Neutron Detection

An operator method has been applied to formulate probability distribution functions of neutron counts in a reactor.

Assuming all statistical events occurring in the reactor to be Markovian, an operator representation of the no count probability for a given time interval is given. The basic equation for the probability is derived from the Kolmogorov-Chapman equation, and the formal solution obtained thereof. Approximate expressions are also given, for two types of detectors—absorption and fission. The effects of moments of order higher than the second are evaluated numerically.

Further development of the operator calculus has yielded relations connecting the waiting time distribution and the interval distribution with the no count probability.     

Possible Application of γ-Ray Spectrometers Based on CdZnTe Detectors

New semiconductor -ray detectors based on CdZnTe have been developed in the last few years, and they are now being widely used. Their advantages are small size and possibility of operating without cooling. In the present work, these detectors are used to measure the radiation from spent fuel assemblies in holding ponds and dry storage sites, unirradiated nuclear materials, and radioactive wastes. The results are analyzed and compared with other types of detectors. The possible applications of CdZnTe-type detectors are determined.