基于DSP系统的多道脉冲幅度分析器设计

介绍了一种基于DSP系统的高性能、低功耗多道脉冲幅度分析器的软硬件设计.硬件设计从提高多道脉冲幅度分析器的数据处理能力和降低系统功耗的角度出发重点介绍了能处理小信号的峰保电路、高速高精度的模数转换电路以及DSP系统及其相关外设接口;软件设计介绍了基于DSP系统的软件模块和基于CPLD的软件编程.还给出了该系统在XR-100CR探测器上测得的Fe的能谱示倒.     

基于CPLD+ARM的多道脉冲幅度分析器设计

介绍了一种基于CPLD+ARM的多道脉冲幅度分析器的设计方案。通过在CPLD内建立FIFO缓存队列,使数据采集和脉冲幅度分析速度协调,提高核脉冲的通过率;采用STM32F10X固件库开发多道分析器软件,可缩短软件开发周期;高集成度、低功耗器件的应用有助于降低多道分析器的功耗并有利于其小型化。CPLD+ARM的实现方案体现出一定的优势。     

基于PDA的便携式X荧光分析仪的研制

研制了一种基于PDA的便携式X荧光分析仪。它采用了高性能C8051F060单片机作为测量控制主板的核心控制器。PDA和测量控制主板采用蓝牙通信。由于C8051F060内含丰富的片上资源,使得多道分析器(MCA)、X光管的控制检测电路、峰值检测电路等的设计都显得非常简洁。PDA平台上运行WinCE操作系统。PDA上的分析软件在Visual Studio2005平台上开发,并采用C++编写软件。采用了高效等离子可充电电池供电。     

基于DSP的数字多道脉冲幅度分析器设计

介绍了基于DSP的数字脉冲幅度分析器的设计.采用TMS320F2812作为数字核信号处理器,将ADC采集到的核信号进行数字积分、寻峰、阈值判别等数字处理,并得到能谱.系统通过USB接口实现数字多道与PC端监控及能谱分析软件的通信.最后本文给出了由NaI(TI)探测器得到的核信号经数字多道处理后,获得137Cs的能谱图.     

CPLD在微机化多道核谱获取系统中的应用

介绍了一种采用EDA技术和CPLD器件的高性能微机化多道核谱获取. 利用CPLD对多道脉冲幅度分析器数字电路进行系统集成的设计原理与方法，对系统的特点和设计中的技术要点作了详细的探讨。     

基于DSP技术的多道核脉冲幅度分析器的设计

介绍以DSP2407芯片为核心,采用专用峰值幅度采样保持电路,根据输入信号上升沿及峰值信息进行分析的多道核脉冲幅度分析器系统的原理和硬件结构.在合金分析及同位素密度成像系统中,采用本脉冲幅度分析器进行高速数据采集,取得了满意的效果.也可适用于其他核脉冲信号峰值幅度分析的场合.     

基于LABVIEW和数字多道脉冲幅度分析器的γ能谱分析软件的开发

基于LABVIEW平台和数字多道脉冲幅度分析器开发了γ能谱分析软件,能实现谱数据光滑、自动寻峰、能量刻度、峰边界道的确定和峰面积的计算,从而完成对γ能谱的定性和定量分析.应用LABVIEW中CIN节点与C语言的结合实现了查找元素的功能.该谱分析软件已用于数字多道脉冲幅度分析器(DMCA)中对γ能谱数据进行分析,可以实现基本的谱分析功能.     

新型数字多道脉冲幅度分析器设计

研制了一款新型通用数字多道脉冲幅度分析器。包括模拟调理电路和数字核脉冲信号处理器与微控制器。在16k道数字转换增益下,单脉冲幅度谱展宽后的FWHM均在2道以内,采用Na I(Tl)探测器实测137Csγ能谱,661.7 ke V处能量分辨率达到了6.89%。     

简易“扫描式”能谱分析器

在穆斯堡尔效应实验中,一般采用完善的多道分析器,可以十分方便地选择出所需的探测器输出的γ射线讯号。但因多道分析器价格太高,在某些情况下,不容易有良好的设备条件。 本工作的目的是企图不用多道分析器,也能直观而敏捷地得到所需的能谱,确定单道脉冲幅度分析器上、下阈值合适的数值。我们更改了单道分析器的电路,采用四路输入、四与门输出电路,则可达到与多道分析器     

数字多道脉冲幅度分析器的硬件电路设计

介绍了基于高速ADC、DSP、FPGA等器件设计实现多道脉冲幅度分析器的硬件电路。该设计提高了仪器的性能,将得到广泛应用。     

图形点阵LCD在手提式多元素X荧光仪中的应用

基于T6963C的图形点阵液晶显示器,功能低、与微机适配接口电路简单、显示方式灵活。介绍了该显示器在电致冷半导体探头手提式多元素X荧光仪应用中,汉字、下接菜单、能谱曲线等显示的编程技巧,及其与嵌入式PC104工控机的实用接口电路。     

RWM-B放射性水连续监测系统

核设施液态流出物的监测是鉴别核设施生产运行是否处于正常状况不可缺少的有力措施，也是评价核设施辐射安全的重要手段。本工作涉及RWM-B放射性水连续监测仪的研制。该监测系统采用高气压氙气电离室作为探测器，以8051单片计算机作为控制主机，电路上采用弱电流测量方法。如果5min 报告1次数据结果，取95%置信度，在普通天然本底条件下，探测下限则可达到2644Bq/m³。     

一种基于高速微控制器的新型便携式多道分析器

介绍了一种基于高速微控制器的新型便携式多道分析器,分析了其硬件电路的实现方法和主机软件的设计思路,此多道具有速度快、体积小、性能较好等特点。     

CMOS电路γ总剂量辐射效应评论

本文从实验结果出发,评论了国产市售和加固CMOS电路抗γ总剂量的辐射特性。介绍了几种工艺CMOS电路阈电压、静态功耗电流、输入输出特性和传输延迟时间等对总剂量辐射的不同响应规则。对多种实验电路进行了为期两年的辐射特性退火观察。实验的同时,对美国RCA公司的一种未加固电路作了辐射测量。用该结果与国产电路的辐射特性作了比较。本文认为~(6O)Co源可以作为合适的核爆总剂量辐射效应模拟源。     

C8051F020单片机在热释光剂量读出器中的应用

详细介绍了基于C8051FD20单片机的热释光剂量读出器的硬件设计,包括主控模块、温度控制模块、人机交互模块、数据存储模块等.采用C8051F020单片机研制的热释光剂量读出器较以往读出器体现出以下优点:设计效率大大提高,外围芯片减少,成本降低,由于硬件系统高度集成,使得读出器性能更加可靠、稳定,运行速度快.     

NMIS plus gamma spectroscopy for attributes of HEU,PU and HE detection

A combined nuclear materials identification system–gamma ray spectrometry system can be used passively to obtain the following attributes of Pu: presence, fissile mass, 240/239 ratio and metal versus oxide. This system can also be used with a small, portable, DT neutron generator to measure the attributes of highly enriched uranium (HEU): presence, fissile mass, enrichment, metal versus oxide; and detect the presence of high explosives (HE). For the passive system, time-dependent coincidence distributions can be used for the presence, fissile mass, metal versus oxide for Pu, 240/239 ratio, and gamma ray spectrometry can also be used for 240/239 ratio and presence, allowing presence and 240/239 ratio to be confirmed by two methods. For the active system with a DT neutron generator, all relevant attributes for both Pu and HEU can be determined from various features of the time-dependent coincidence distribution measurements. Active gamma ray spectrometry would determine the presence of HE. The various features of time-dependent coincidence distributions and gamma ray spectrometry that determine these attributes are discussed with some examples from previous determinations.     

Radiation Hardened CMOS/SOS Memory Circuits

Large-scale-integrated circuits which combine radiation hardness with density, high speed and low power dissipation require both hardened processes and hardened circuit design methods. CMOS/SOS circuits featuring self-compensation, self-biasing and parameter tracking accommodate a wide range of nonuniform on-chip parameter variations. These variations result from exposure to a nuclear radiation event, as well as from MOS device processing, temperature and power-supply effects. The circuits discussed in this paper are key elements for radiation-hardened memory designs [up to 106 rads(Si)] with state-of-the-art LSI density and performance. The CMOS/SOS memory cell sizes of 3.1 mil2 for a six-device, and 2.5 mil2 for a four-device, static cell are nearly five times smaller than previous radiation-hardened designs.     

The design of the Fort St. Vrain steam generators

The steam generators for the Fort St. Vrain nuclear power plant are the first application in the United States of once-through boiler design coupled with a high temperature gas-cooled reactor. They contain many design features which are unique for this type of component. Since they are an integral part of the primary system and completely enclosed by the prestressed concrete reactor vessel, they must be removable as well as fit the space available for penetrations. These requirements made the once-through boiler principle a logical choice. Multi-start helically wound tubes supported by perforated plates in a star-shape arrangement resulted in an extremely compact design. The helium inlet temperature of 1427°F and steam temperatures of 1005°F main and 1001°F reheat required unique solutions in terms of flexibility and cooling of support systems and selection of insulation materials and design. Operation in a helium atmosphere without a protective oxide layer called for materials with good wear protection characteristics where parts may experience relative motion. Stabilizing orifices, externally adjustable at the steam generator inlet, plus essentially equal tube lengths for each of the many parallel circuits are utilized to balance circuit performance. To minimize gas bypass flows, special gas seals are provided around individual tube bundles. Field erection time was minimized by developing an upper and a lower module assembly and joining them after erection in the reactor vessel.