可用于核物理监控系统的microC/OS-Ⅱ片上系统的研究

论述了一种基于FPGA和实时操作系统microC/OS-Ⅱ、适用于核物理数据检测和实验控制的片上可编程系统SOPC(System On a Programmable Chip)的设计,并在altera-stratix-Ⅱ2S60f1020c3芯片内获得实现.该片上可编程系统的硬件处理器和实时操作系统都可根据需求裁剪、重配置.     

先进超导托卡马克实验装置等离子体密度远程控制系统

在先进超导托卡马克实验装置实验阶段,与密度控制有关的实验数据和信息存储在实验现场的计算机系统中,对这些数据进行分析研究时需要到现场才能采集或获取.设计了托管控件,用于等离子体密度远程控制系统业务逻辑的封装,实现了增强型的B/S计算结构,解决了远程控制过程中复杂的科学计算,并实现了实验进程的同步监视.还在数据交换机制中部署了web services和Data File services两层服务,有效地维护了数据传数链路的松散耦合特性.实验证明,它不仅实现了密度的远程控制功能;而且在目前的托卡马克实验情况下,具有较好的数据传输性能.     

小型辐照样品快速传输系统研制

为减少操作人员在样品辐照实验中受到的辐照剂量,进行了以气动控制实现小型辐照样品快速传输的研究.快速传输系统气动回路的通断以及换向控制等由电气控制部分实现.主程序实施系统的初始化,并检测手动/自动转换开关位置,调用相应的子程序实现手动或自动操作.自动子程序实现辐照样品到前端样品存储盒的自动传输;手动子程序完成系统的放气、辐照样品的前进和后退等功能.本文从硬件和软件设计两方面详细介绍了该系统的实现方法.     

高能电子成像直线加速器低电平控制系统研制

为了能开展高能电子成像相关实验研究,中国科学院近代物理研究所建造了一台S波段的射频电子直线加速器。为保证实验用束流品质和加速器稳定运行的要求,设计了一套低电平控制系统,利用上下变频、IQ解调技术,实现了相位的反馈控制。本文介绍了低电平控制系统的设计及数字化算法的实现,给出了系统闭环实验的测试结果,实现相位控制精度达到±0.5°(峰峰值)和0.110 8°(均方根)。该系统利用成熟的商业化模拟微波器件和相关的PXI板卡实现,基于LabVIEW软件开发了相关的控制程序和界面,具有搭建方便、开发时间短、结构简单紧凑、易于使用和维护的特点。     

闭环控制在离子源放电实验中的应用

本文介绍了闭环反馈控制离子源充气系统的研制.该系统通过A/D模数转换和D/A数模转换完成系统数字信号处理的输入与输出.并由软件实现数字PID控制器,通过参数的调整完成阀门的控制,取得了很好的实验结果.文中讨论了系统构成与实验结果.     

EAST 2MW/2450MHz低杂波电流驱动系统综述

为了研究全超导托卡马克稳态高参数等离子体性能,2008年在EIAST装置上研制并成功建成了-套最大能传输2兆瓦,工作频率是2450MHz的低混杂波电流驱动系统.该系统主要由20个速调管放大器、4套高压源、20路每路30～40米长的WR430标准矩形波导传输线和多结波导天线阵列组成.辐射波谱的控制是通过子波导内的固定移相器和微波前级的数字可调移相器两种移相手段来实现.在低杂波系统的辅助下成功实现了:驱动中心密度为1～2×1013cm-3下150～500kA的等离子体,全波驱动250kA电流达23s和低杂波辅助启动实验,所有的这些实验都证明了整个低杂波系统的稳定和可靠性.详细描述了整个系统的构成和初步的实验结果.     

高能电子成像直线加速器低电平控制系统研制

为了能开展高能电子成像相关实验研究,中国科学院近代物理研究所建造了一台S波段的射频电子直线加速器。为保证实验用束流品质和加速器稳定运行的要求,设计了一套低电平控制系统,利用上下变频、IQ解调技术,实现了相位的反馈控制。本文介绍了低电平控制系统的设计及数字化算法的实现,给出了系统闭环实验的测试结果,实现相位控制精度达到±0.5°(峰峰值)和0.110 8°(均方根)。该系统利用成熟的商业化模拟微波器件和相关的PXI板卡实现,基于LabVIEW软件开发了相关的控制程序和界面,具有搭建方便、开发时间短、结构简单紧凑、易于使用和维护的特点。     

基于ARM7S3C44B0X01的数据采集系统的设计与实现

本文对一套基于ARM的嵌入式数据采集系统的设计与实现作了介绍,该数据采集系统不仅能作用于温湿度等常规信号,而且能对核脉冲等快速变化的信号进行采集和处理.系统以S3C44BOX01为核心控制单元,加上ADS774的模数(A/D)转换功能,能够保持在较低功耗下实现对外来信号进行快速精确地获取.     

PRS换热器蒸汽凝结换热模型研究

使用RELAP5/MOD3.2程序对某型核动力装置二次侧非能动余热排出系统(PRS)1:1实验装置进行稳态计算,一些工况下计算结果同实验结果偏差较大。研究了汽-液界面剪切应力及系统高压等条件对层流和湍流状态下竖直管内蒸汽凝结模型的影响,并对模型进行了改进。改进后的RELAP5程序对该系统1:1实验装置进行稳态和瞬态计算,计算结果同实验结果符合良好。     

光束线站EPICS数据采集系统研究

上海光源光束线控制系统采用标准软硬件平台开发完成.为实现XBPM测量及电离室等探测器要求的运动控制与信号采集的联动集成,本文用Hytec公司的ADC/DAC模块建立一套VME/IOC的EPICS数据采集系统.经光束线在线测试,该系统完全可应用在XBPM同步光位置诊断、单色器能量控制与探测器信号同步采集等相关用户实验中.     

Design of Main Control Console Software in EAST Neutral Beam Injector’s Control System for the First Beam Line

Neutral beam injector is one of the main plasma heating and plasma current driving methods for experimental advanced superconducting tokomaks (EAST). In order to realize visual operation of EAST neutral beam injector’s control system (NBICS), main control console (MCC) is developed to work as the human–machine interface between the NBICS and physical operator. It can meet the requirements of visual control of NBICS by providing a user graphic interface. With the specific algorithms, the setup of power supply sequence is relatively independent and simple. Displaying the real-time feedback of the subsystems provides a reference for operators to monitor the status of the system. The MCC software runs on a Windows system and uses C++ language code while using client/server (C/S) mode, multithreading and cyclic redundancy check technology. The experimental results have proved that MCC provides a stability and reliability operation of NBICS and works as an effective man–machine interface at the same time.     

基于ARM、CPLD和MCU的冷却储存环真空控制系统设计

为核心进行实时多路数据采集和控制的冷却储存环（CSR）真空控制系统设计。着重分析了控制系统组成、工作原理、功能实现、硬件电路和软件开发。该控制系统具有适应性与灵活性强、响应速度快、精度高、稳定性好、可靠性高、性价比优越、自我连锁保护等优点，现已成功应用于CSR真空控制系统中。     

上海同步辐射光源工作点稳定性研究

上海同步辐射光源（SSRF）是一台第3代高性能同步辐射装置,已稳定运行超过10年。储存环的线性光学模型稳定是光源稳定运行的基础。工作点反馈系统可实时地校正工作点,并间接地以降维的方式反馈难以在线测量到的线性光学函数。工作点反馈系统在SSRF的稳定运行验证了此方法的可行性,该反馈系统不仅使得工作点稳定度显著提升,也使得束流发射度、注入效率以及束流寿命等重要参数的稳定度得到大幅提升。衍射极限储存环光源是现阶段被广泛研究和建设的新一代同步辐射光源,工作点反馈系统也将发挥更重要的作用。本文分析电子储存环线性光学函数和工作点的稳定性,回顾SSRF工作点反馈系统的实际运行情况,介绍工作点反馈系统在SSRF衍射极限环lattice（SSRF-U）的模拟。工作点反馈在SSRF的实际运行情况和在SSRF-U的模拟结果显示,该系统可将工作点稳定在±0.001范围内,可满足储存环光源稳定运行和线性差耦合共振圆束斑模式对工作点稳定度的需求。     

Low level gas multicounter for 14C dating of small samples

A compact gas multicounter has been constructed and is undergoing tests. Up to 14 methane samples can be counted simultaneously in an array of 10 ml (at NTP) copper counters at a pressure of 1–8 bar. The gas filling, application of high voltage and decay energy monitoring are microprocessor controlled. Multichannel analyses (256 ch. sample and cosmic detector energy data), sample identity, counting time and critical validity parameters are stored on disc. Numerical discrimination and manipulations of counting parameters can be performed without destroying the original data set. Statistical quality control is based on chi-square and Poisson distribution of countrates around their mean in user defined energy regions as well as “ time of arrival” (TA) of pulses mode. TA analysis offers the user an early means of recognition of some types of system malfunction that otherwise might remain undetected for long periods of time. Pulse shape analysis is used to discriminate sample beta from environmental radiation pulses resulting in a low background with compact and relatively inexpensive shielding.     

The Need for Flexibility in Amplifier Design

Improvements in detector resolution and increases in the sophistication of nuclear experiments have placed an entirely new emphasis on linear amplifier design. Just a few years ago it was necessary to have specialized amplifiers to deal with each specific problem. The lack of flexibility now plaguing most existing linear pulse amplifying systems is often quite annoying to the user. Invariably, the user will find the amplifying system failing in part to provide either adequate stability, polarity reversibility, clipping mode selection, control of rise and fall times, adequate control of gain, or threshold cut and expansion. What usually ensues is that large amounts of time and effort are expended in modifying existing amplifiers in order to accomplish the particular job at hand, or the Job is done with an existing system where poor amplifier performance is accepted as a necessary evil. In the past several years many notable pulse amplifiers have been produced. Among these are the DD-2, the A-8, and the alpha amplifiers designed under the direction of Fairstein, Borkowski, and Blankenship at the Oak Ridge National Laboratory. Although these amplifiers show exceptional performance in their particular specialized application, all of these amplifiers lack the flexibility desired in a modern general-purpose laboratory amplifier. What is needed today is an amplifying system possessing the best basic features of these highly successful amplifiers with the addition of the features mentioned earlier to obtain greater flexibility and therefore greater utility. In early 1961, an amplifying system of this type was introduced at LRL.     

Neutron noise induced by vibration on the French PHENIX LMFBR

The vibratory measurements which are available on the reactor have simultaneously been recorded with the fluctuations of neutronic power measurements. We observed:

1. 1°) A movement of the carrier concrete slab of the primary circuit at the fundamental frequency corresponding to the pumps rotary speed.

2. 2°) A low level vibration on a control rod drive corresponding to an incipient defect.

3. 3°) Vibrations emergence on the core cover during a working cycle.

4. 4°) All the time, a resonance corresponding to the first vibrational mode of the fuel assemblies under the cooling sodium flow.

The evidence of the vibratory movement has been obtained by the systematic calculation of the coherence function between the available neutronic noise measurements and the vibratory transducers.

From the experience gained on PHENIX vibrations measurements are included in the SUPER PHENIX monitoring system.     

Development of a simulation platform for studying on primary frequency regulation characteristics of nuclear units

With the rapid development of nuclear units, the primary frequency regulation (PFR) characteristics of nuclear units have a significant affect on the frequency stability of power system. Power system will suffer great challenge if nuclear units do not participate in PFR, so study on the PFR characteristics of nuclear units has becoming a pressing issue. A detailed, nonlinear, time-varying dynamic mathematical model of a whole pressurized water reactor (PWR) nuclear power plant has been established in the present study. The simulation platform for studying on the PFR characteristics of nuclear units has been developed according to the model established. Using the simulation platform, the operation and control mode of PWR nuclear units participating in PFR of power system is simulated and studied. The simulations results show that PWR nuclear units are feasible in participating in PFR from safety and economy by adopting the operation and control mode presented in the study, which can contribute to the practical operation of power system.     

Plasma profile and shape optimization for the advanced tokamak power plant, ARIES-AT

An advanced tokamak plasma configuration is developed based on equilibrium, ideal MHD stability, bootstrap current analysis, vertical stability and control, and poloidal field coil analysis. The plasma boundaries used in the analysis are forced to coincide with the 99% flux surface from the free-boundary equilibrium. Using an accurate bootstrap current model and external current drive profiles from ray tracing calculations in combination with optimized pressure profiles, β_N values above 7.0 have been obtained. The minimum current drive requirement is found to lie at a lower β_N of 6.0. The external kink mode is stabilized by a tungsten shell located at 0.33 times the minor radius and a feedback system. Plasma shape optimization has led to an elongation of 2.2 and triangularity of 0.9 at the separatrix. Vertical stability could be achieved by a combination of tungsten shells located at 0.33 times the minor radius and feedback control coils located behind the shield. The poloidal field coils were optimized in location and current, providing a maximum coil current of 8.6 MA. These developments have led to a simultaneous reduction in the power plant major radius and toroidal field from those found in a previous study [S.C. Jardin, C.E. Kessel, C.G. Bathke, D.A. Ehst, T.K. Mau, F. Najmabadi, T.W. Petrie, the ARIES Team, Physics basis for a reversed shear tokamak power plant, Fusion Eng. Design 38 (1997) 27].     

A VAX Based Data Acquisition Computer System at the Nuclear Structure Research Laboratory

The Nuclear Structure Research Laboratory at the University of Rochester is developing a VAX-11/750 computer system for use in a data acquisition and analysis system. The system consists of the VAX which is networked to two LSI-11/23's which are in turn connected to CAMAC branch drivers. The CAMAC branch drivers operate both parallel and 5 MHz byte-serial highways. The network is a high speed DMA interface and is identical to the system implemented at the W.K. Kellogg Radiation Laboratory[l]. The data acquisition system has been designed to allow the user to select standard program modules as building blocks to construct a system to suit the particular needs of the experiment. The division of the realtime analysis between the VAX and the LSI-11s is flexible. The LSI-11s are equipped with small array processors tlo permit high speed analysis on the satellite processors.