120路簇射计数器读出电子学系统

120路簇射计数读出电子学系统,主要由采样保持电路、多路模拟数字转换器及模拟总线组成。为了提高整个系统的装配密度和可靠性并减小环境温度变化的影响,专门设计了一种薄膜混合集成采样保持电路。采用了计算机在线校正方法,解决了放大器增益变化、积分非线性、模拟开关台阶和传输电缆干扰等引起的测量误差问题。系统的主要指标为:线性优于0.2％,σ噪音约为1.3BADC道,串扰优于1％,Z向位置分辨优于0.6％(SQS簇射计数器模型)。     

北京谱仪端盖簇射计数器的监测系统

大型探测器的监测系统是实时监测探测器性能,保证其正常运行以及提供校正参数不可缺少的部分。本文介绍了北京谱仪端盖族射计数器监测系统的结构、性能及其在北京谱仪运行取数过程中的监测结果。     

Performance of a Thallium Chloride Scintiliator as a Total Absorption Shower Cascade Detector

Studies have been made of the performance of a large sample of the new heavy scintillator TlCl(Be,I) as a total absorption shower cascade (TASC) detector for high energy electrons and gamma rays. The observed energy resolution for electrons in the range 0.1 to 15 GeV is reported and compared to a Monte Carlo calculation of expected fluctuations in energy leakage from the crystal volume. The performance of this new scintillator and its potential applications are discussed.     

BES 桶部簇射计数器工作特性的测量

本文给出了ＢＥＳ桶部簇射计数器工作特性的一些测量结果。用５５ＦｅＸ射线源测量了工作气体的气体放大特性曲线和气体入出口的坪特性曲线，测量了输出脉冲电荷量的稳定性。用宇宙线μ子测量了桶部簇射计数器不同并联单元的坪特性曲线。用Ｂｈａｂｈａ散射测量了桶部簇射计数器的能量分辨与位置分辨。     

The Mark II silicon strip vertex detector and performance of asilicon detector telescope in the Mark II detector at the SLC

A silicon strip vertex detector (SSVD) consisting of 36 independent silicon detector modules has been built for use in the Mark II detector at the SLAC Linear Collider (SLC). The performance of the individual modules and the stability and accuracy of their placement in the mechanical support are discussed. Top gain operational experience at the SLC, a telescope made of three silicon detector modules has been assembled and placed inside the Mark II. Results from the first data run of the SLC on the overall performance of the telescope, including backgrounds, charged particle tracking, and spatial resolution, are presented     

用恒流技术改进液闪中电荷灵敏放大器的性能

在液闪电子线路中,有各种各样的电荷恒流技术,本文重点强调恒流、电荷技术及在液闪中的应用。     

基于光电二极管阵列的二维成像数据采集系统研究

本文研制了—套基于多像素光子计数器阵列(MPPC)的H_α辐射光二维高速成像系统~([1]),通过对微弱H_α辐射光的成形放大、模数转换和数据处理,实现了128通道高达1Mfps的二维成像系统。该系统用于研究托卡马克聚变实验中的加料过程,通过测量氘分子同等离子体相互作用产生的H_α辐射光的空间分布图像,获得超声分子柬的密度、空间分布等参数随时间的演化过程,是适用于托卡马克聚变装置的重要诊断技术之一。     

基于MCNP模拟的中子多重性计数器3He管的设计

为设计高性能的中子多重性计数器,采用MCNP4C计算软件建立3He管计算模型,模拟计算3He管的参数对多重性计数器探测效率的影响,针对中子多重性计数器中3He管进行了初步设计,以满足中子多重性测量要求。     

闪烁体探测器在田湾核电站辐射监测系统中的应用

以GLM201 -1液体γ活度监测仪为代表介绍了闪烁体探测器在田湾核电站辐射监测系统中的应用并对该仪器的结构、原理、使用情况进行了初步研究.     

Accident scenarios of the TRIGA Mark II reactor in Vienna

The safety report of the TRIGA Mark II reactor in Vienna includes three accident scenarios and their deterministic dose consequences to the environment. The destruction of the cladding of the most activated fuel element, the destruction of all fuel elements and a plane crash were considered scenarios in that report. The calculations were made in 1978 with the software program named STRISK. In this paper, the program package PC Cosyma was applied on the TRIGA Mark II reactor in Vienna and the deterministic consequences of the scenarios to the environment were updated. The fission product inventories of all fuel elements were calculated with ORIGEN2. To get meteorological data of the atmospheric condition around the release area, a weather station was installed. The release parameters were taken from the safety report or were replaced by worst case parameters. This paper focuses on two accident scenarios: the destruction of the cladding of the fuel element with the highest activity content and the case of a large plane crash. The current accident scenarios show good agreement with the calculations from 1978, hence no technical modifications in the safety report of the TRIGA reactor Vienna were necessary. Even in the very worst case scenario – complete destruction of all fuel elements in a large plane crash – the expected doses in the Atominstitut's neighborhood remain moderate.     

快响应束流损失监控(FBLM)系统液闪探测器初样的研制

给出快响应束流损失监控(Fast Beam Lost Monitor,FBLM)系统的液体闪烁体探测器初样的研制.在高频四极加速器(Radio Frequency Quadrupole,RFQ)实验装置上的测试表明,液闪探测器能给出宽度为500 μs 束流宏脉冲结构,能逐个显示出宏脉冲内490 ns的束流切束脉冲.液闪...     

SiPM用于闪烁探测器的性能研究

为进一步发挥硅光电倍增管(Si PM)在闪烁探测器体的作用。采用Si PM与塑料闪烁体光导耦合搭建的探测器,对Si PM的偏压特性、温度特性、抗磁场性能和耐辐照性能进行了实验测试,给出相应的测试数据并对测试数据进行分析,分析结果表明该测试数据可用于指导Si PM在实际工程中的应用。     

Neutronics analysis of the initial core of the TRIGA Mark II reactor

The Atominstitute (ATI) of Vienna University of Technology (VUT) operates a TRIGA Mark II research reactor since March 1962. Its initial criticality was achieved on 7th March 1962 when 57th Fuel Element (FE) was loaded to the core. This paper describes the development of the MCNP model of the TRIGA reactor and its validation through three different experiments i.e. initial criticality, reactivity distribution and a thermal flux mapping experiment in the reactor core. All these experiments were performed on the initial core configuration. The MCNP model includes all necessary core components i.e. FE, Graphite Element GE, neutron Source Element (SE), Central IRradiation channel (CIR) etc. Outside the core, this model simulates the annular grooved graphite reflector, the thermal and thermalizing column, four beam tubes and the reactor water tank up to 100 cm in radial and +60 and −60 cm in axial direction. Each grid position at its exact location is modeled. This model employs the ENDF/B-VI data library except for the Sm-isotopes which are taken from JEFF 3.1 because ENDF/B-VI lacks samarium (Sm) cross sections.For the first experiment, the model predicts an effective multiplication factor (κ_eff) of 1.00183 with an estimated standard deviation 0.00031 which is very close to the experimental value 1.00114. The second experiment measures the reactivity values of four FE and one GE. In comparison to the MCNP results, the percent difference ranges from 4 to 22. The third experiment verifies the model at a local level with the radial and axial thermal flux density distribution in the core. Though the trends are similar, the MCNP model overestimates the radial thermal flux density in the core and underestimates these results at the core periphery.     

A Measurement of the Energy Resolution and Related Properties of an SCG1-C Scintillation Glass Shower Counter Array for 1-25 GeV Positrons

We report the measurement of the energy resolution of a 4×4 array of SCG1-C scintillation glass counters (Ohara Optical Glass Manufacturing Co., Ltd.) exposed to positrons in the energy range of 1 to 25 GeV. Each element of the array was 20.5 radiation lengths long. The resolution of the array was measured both with and without a 3.5 radiation length SCG1-C scintillation glass active converter and 0.2 radiation length hodoscopes used to measure shower position. We obtained an energy resolution ?/E = (1.63 + 1.46/?E)% without the active converter and ?/E = (0.64 + 3.94/?E)% with the active converter. Performing a partial correction for the average energy loss in the 0.2 radiation length hodoscopes resulted in an energy resolution of ?/E = (0.50 + 3.43/?/E)% for the active converter measurement. We also report on the measurement of the absolute number of photons produced by 1 GeV showers, the optical attenuation length for the light produced by showers, the fraction of the total light output that is due to Cerenkov light relative to scintillation light for showers, and the radiation darkening sensitivity of the scintillation glass.     

常压下RRA系统性能试验分析

余热排出系统(RRA)能将反应堆冷却剂温度维持在冷停堆工况,并可满足换料和维修操作所需要的时间。在维修冷停堆工况下(堆芯有燃料),保证任何一台蒸汽发生器维修时,维持冷却剂温度低于60℃,使维修人员能够进入蒸汽发生器人孔,同时还要保证堆芯的冷却。本试验需要验证在此工况下,在主管道环路高液位报警出现时,反应堆冷却剂不会进入蒸汽发生器底封头而造成工作人员额外的放射性污染。在主环路低液位报警时,余热排出泵在单泵设计要求的最大流量下运行时,不会发生汽蚀。当维修冷停堆工况下投用三环路热段主管道环路液位计RCP300MN时,液位的升降应足够缓慢,以避免液位变化过快而引起的仪表显示故障。     

二轴中子粉末衍射谱仪探测系统改进

通过将探测器的数目由1个增加到4个、用水平发散角为20′的Soller准直器取代30′的单缝准直器，对中国原子能科学研究院重水研究堆旁的二轴中子粉末衍射谱仪进行了改进。铁粉的衍射实验结果表明：改进后的谱仪在同等中子计数强度条件下，计数速率提高了2．3倍，因而缩短了测量时间，同时也提高了谱仪的分辨率。     

Note on the Performance of an Improved Light Guide for a Beta-Ray Detector

The performance of an equiangular spiral light guide for a beta-ray detector is compared with a conventional straight light guide. An improved signal to noise ratio was obtained using the equiangular spiral light guide.     

Description and Performance of a VAX 11/750 - MBD Computer System at the University of Manitoba Cyclotron Laboratory

A data acquisition and analysis facility based on a VAX 11/750 computer interfaced to a CAMAC crate via a MBD-11 Branch Driver is described. Factors influencing the choice of the system and problems resulting from the specific choices, along with their resolution, are discussed. Finally, some performance figures for the data acquisition software, as well as an example of the type and complexity of the experiments which can be performed with the facility, are provided.