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1.
陶瓷真空室研制及其阻抗的研究   总被引:3,自引:0,他引:3  
介绍了电子储存环注入凸轨击磁铁及春真空室常采用的几种技术方案。合肥电子储存环新凸轨注入系统选择了铁氧体磁铁内置陶瓷真空室的方式。为了同时满足脉冲磁场穿透性能及束流耦合阻抗的要求,陶瓷真空室的内壁须镀1层金属薄膜。  相似文献   

2.
为了提供35块四极磁铁在800 MeV电子储存环上的编组排列的数据,研制了一台称为“四极铁比较测量”的测量系统。文章描写了该系统的测量原理和方法,并且给出了测量结果,最后对测量结果的误差进行了讨论。  相似文献   

3.
介绍了兰州重离子加速器冷却储存环中束流位置测量系统设计的基本原理、PICKUP探针参数的选择以及有关物理的计算。并完成了桌上实验,得出了有关结论。  相似文献   

4.
介绍了NSRL电子储存环束流损失监测系统的分布式数据采集系统构成,并详细介绍了其中的下位机结构,计数器设计以及CAN BUS总线等技术研究。  相似文献   

5.
合肥光源的工作点测量系统   总被引:5,自引:0,他引:5  
合肥 8 0 0MeV电子储存环的工作点测量系统采用扫频激励法进行工作点测量 ,它由条带束流位置检测器、180 0 的魔T、混频器、带扫频信号输出的频谱分析仪、功率放大器和束流激励电极等构成。该系统的测量精度约为 1× 10 4 。利用该系统进行了机器的校正色品测量 ,给出了工作点和色品的测量结果。  相似文献   

6.
电子储存环中损失的束流电子,在撞击真空室壁时,引起“电子-γ-电子”簇射,在撞击点的下游,真空室的外表面形成次级电子(shower电子)的分布。通过探测这些shower电子,可以知道上游某处的束流损失状况。“合肥国家同步辐射实验室加速器二期工程”中的电子储存环束流损失监测系统,就是利用这个原理。在分析了原有加速器束流损失监测系统的缺陷并对国际上各大型加速器进行了调研的基础上,对该系统中的探测器选型、探测器安装位置的选择以及系统的整体结构等物理问题作了阐述。  相似文献   

7.
用20GHz数字取样示波器测量束团长度   总被引:4,自引:0,他引:4  
介绍了采用20GHz数字取样示波器在合肥800MeV电子储存环中测量束团长度的方法和原理。给出了束团长度及其伸长效应的测量结果。在流强为2-124mA情况下,实测束团长度为3.80-10.33cm;流强大于15mA,束团伸长效应明显。  相似文献   

8.
冷用斌  王霁虹 《核技术》1997,20(6):374-377
介绍了合肥国家同步辐射实验室800MeV电子储存环主电源控制系统中VME总线ramping板的设计及研制过程。  相似文献   

9.
高能电子和物质相互作用是一个级联簇射(shower)物理过程。NSRL电子储存环(HLS)束流损失监测系统利用这一原理,通过探测束流损失电子在储存环真空室外表面产生的shower电子,给出束流损失的有关信息。本文利用Monte-Carlo方法,采用EGS4软件包,对束流损失电子与真空室壁相互作用的过程进行模拟,给出了真空室外表面shower电子的分布特点(1)shower电子在真空室外表面是前冲性很强的粒子;(2)在垂直方向的分布是比较窄的对称分布,对束流损失探测器的安装有一定的要求;(3)打在真空室内侧壁上的电子及其产生的shower电子有机会反射到外侧壁,并进一步发生shower过程,但其影响会低两个量级以上;(4)shower电子在真空室外表面上的分布,外侧峰位要比内侧峰位位置在束流方向上后移。  相似文献   

10.
11.
On the experimental advanced superconducting tokamak(EAST), a pair of voltage and current probes(V/I probes) is installed on the ion cyclotron radio frequency transmission lines to measure the antenna input impedance, and supplement the conventional measurement technique based on voltage probe arrays. The coupling coefficients of V/I probes are sensitive to their sizes and installing locations, thus they should be determined properly to match the measurement range of data acquisition card. The V/I probes are tested in a testing platform at low power with various artificial loads. The testing results show that the deviation of coupling resistance is small for loads RL??2.5 Ω, while the resistance deviations appear large for loads RL??1.5 Ω, which implies that the power loss cannot be neglected at high VSWR. As the factors that give rise to the deviation of coupling resistance calculation, the phase measurement error is the more significant factor leads to deleterious results rather than the amplitude measurement error. To exclude the possible ingredients that may lead to phase measurement error, the phase detector can be calibrated in steady L-mode scenario and then use the calibrated data for calculation under H-mode cases in EAST experiments.  相似文献   

12.
一种复合屏蔽电缆的转移阻抗   总被引:1,自引:0,他引:1  
给出一种复合屏蔽电缆转移阻抗的测试方法和结果,从测试结果可看出.在低频下.转移阻抗为电缆屏蔽的直流电阻;在高频段(大于30MHz).转移阻抗随着频率的增加而增加.其屏蔽性能优于单层屏蔽结构的电缆。  相似文献   

13.
屏蔽电缆转移阻抗的测量   总被引:4,自引:1,他引:4  
介绍了一种快速有效地测量电缆转移阻抗的方法,给出了SYVZ-9综合电缆转移阻抗的测试结果,从测试结果可以看出,在低频下,转移阻抗为电缆屏蔽层的直流电阻,随着频率的增加,转移阻抗迅速增加。  相似文献   

14.
In this paper,higher order modes(HOMs) and loss factor of a new type of 500-MHz superconducting cavity is studied,by simulating its broadband HOMs damping at different positions of the ferrite HOM-absorber and different lengths of the ferrite.The results show that the impedance and Q value of the HOMs in transverse and longitudinal modes could be greatly reduced.The HOM longitudinal impedance could be damped to meet the requirement of SSRF beam instability threshold.The calculated loss factor of the new SC cavity was compared with cavities at SSRF.It was estimated that the HOM absorber could absorb a total power of 3.16 kW at 4-mm beam bunch length.  相似文献   

15.
报道了用金属弹丸在不同的压力下超高速撞击地表矿物方解石和灰岩时所含挥发成分CO2 释放和TL强度减弱的结果。试图探讨自然界方解石和灰岩受陨石冲击后CO2 释放量与TL强度的关系 ,总结用TL强度来估算方解石和灰岩受冲击后CO2 释放量的简单而直接的方法  相似文献   

16.
Experiments are carried out to investigate the effects of the natural convection of superheated gas as well as those of the standpipes on the temperature distributions of the components and the heat removal performance in the water-cooling panel system for the MHTGR for decay heat removal, and to verify reliability of the design and evaluation methods. The numerical results of the code THANPACST2 are compared with the experimental data to verify the numerical methods and axi-symmetric model proposed, which can simulate the three-dimensional configuration of the standpipes on the upper head of the pressure vessel by using porous body cells. The experiments revealed that temperatures increased with elevation on the upper head, because the standpipes restrict radiation heat transfer to the upper cooling panel and reduce the heat transfer area on the upper head, which was superheated by natural convection of helium gas in the pressure vessel. In the presumed accident condition in which thermal radiative heat transfer is responsible for the majority of the total heat transfer, the numerical methods were able to closely duplicate the pattern of the rising temperature profile with elevation around the top of the upper head as observed in the experiments.  相似文献   

17.
基于StrataGem(EH4)大地电磁测量仪的实测数据,剖析了该系统计算阻抗过程(IMAGEM软件完成)中两个重要不足。一个是以常相干度为工具控制由机械叠加形成的原始谱而计算互功率谱过程,容易造成放大单个原始谱点在互功率谱计算中的作用,也可能舍弃了许多有用信息;另一个是以最小二乘算法估算阻抗容易造成所估算的阻抗不稳定。  相似文献   

18.
介绍了固体径迹火花计数器的研制,结合已有火花计数器的特点对火花计数器结构进行了优化,并设计实验对火花计数器的部分性能进行了研究分析,通过实验得出了影响火花计数器性能因素,找到了该火花计数器能够较准确计数的最佳工作条件。使得本火花计数器能够较准确地读出聚酯膜固体径迹探测器上的径迹信息,更好地应用于氡的测量。  相似文献   

19.
In MTR research reactors, heat removal is, safely performed by forced convection during normal operation and by natural convection after reactor shutdown for residual decay heat removal. However, according to the duration time of operation at full power, it may be required to maintain the forced convection, for a certain period of time after the reactor shutdown. This is among the general requirements for the overall safety engineering features of MTR research reactors to ensure a safe residual heat removal. For instance, in safety analysis of research reactors, initiating events that may challenge the safe removal of residual heat must be identified and analyzed.In the present work, it was assumed a total loss of coolant accident in a typical MTR nuclear research reactor with the objective of examining the core behavior and the occurrence of any fuel damage.For this purpose, the IAEA 10 MW benchmark core, which is a representative of medium power pool type MTR research reactors, was chosen herein in order to investigate the evolution of cladding temperature through the use of a best estimate thermalhydraulic system code RELAP5/mod3.2.  相似文献   

20.
描述了上海同步辐射装置(SSRF)平移长线圈磁测机的设计和制造。磁测机包括的硬件主要有:测量线圈、直线运动平台、高精度数字积分仪、步进电机控制卡、高稳定度电源、直流电流传感器、6位半数字电压表、通用接口总线(GPIB)接口卡及高精度编码器等。磁场测量和数据分析程序采用LabVIEW编制。该磁测机已测量了SSRF储存环二极磁铁的样机,效果良好,能做到灵活、快速和自动化地测量积分场。  相似文献   

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