共查询到20条相似文献,搜索用时 234 毫秒
1.
为了对质子照相束流线设备进行远程监测与控制,实现束流线各子系统的安全联锁功能,研制了一套采用标准控制模型结构的分布式EPICS控制系统。该控制系统通过PLC组态实现了开关逻辑设备的安全联锁及工艺流程控制。核心控制系统采用EPICS建立了多个IOC作为控制器。针对不同CPU构架下的服务器搭建了交叉编译环境。针对数字电源设备与真空仪表设备使用StreamDevice完成设备驱动及通信协议的开发,并通过建立IOC动态数据库,实现了IOC对流设备和PLC信号的监测与控制功能。使用CSS设计OPI,实现了上位机对EPICS IOC中数据的透明访问。该束流线控制系统已成功应用于CYCIAE-100回旋加速器的质子照相物理实验中。通过长时间的运行,控制系统的可靠性、安全性得到了验证。控制系统的稳定运行,为质子照相实验的开展奠定了基础,对类似的控制系统研制具有一定的参考价值。 相似文献
2.
本文对320 kV全离子综合实验平台的控制系统升级进行了研究。升级后的控制系统采用分布式系统模型构建。硬件采用串口服务器、PLC及伺服电机等部件实现了所有被控设备的远程监测及控制。软件通过建立EPICS IOC动态数据库,实现了对所有被控设备的集成。用户操作界面层采用CSS开发,实现了操作人员对所有被控设备的透明访问。该控制系统已成功连续运行约10 000 h。目前该控制系统运行稳定、可靠,完全满足320 kV全离子综合实验平台的运行及物理实验的需求。 相似文献
3.
在核电厂数字化仪表控制系统中使用智能设备可以提高核电厂的故障诊断能力和实时信息监控能力。本文综合考虑核电厂工艺系统特点和测控点分布等因素,设计了不同类型智能设备与核电厂数字化仪表控制系统的通讯接口方案。给出了核电厂数字化仪表控制系统的总体结构和接口方式,详细分析了现场总线型智能设备、第三方成套系统、远程I/O系统、辅控网系统、智能无线网络系统等智能设备接口设计方案。该接口设计方案实现了智能设备与核电厂数字化仪表控制系统的系统集成,提升了核电厂数字化仪表控制系统的控制性能和设备管理能力。 相似文献
4.
5.
6.
7.
ADS注入器Ⅱ真空控制系统设计 总被引:2,自引:1,他引:1
ADS注入器Ⅱ真空控制系统是基于分布式实时控制软件EPICS架构设计的。采用基于数据流设备的通信驱动模块StreamDevice、CSS和JDBC等技术,实现对现场真空设备的远程网络监控和设备状态历史数据查询。对EPICS设备层控制接口采用IOC驱动模块StreamDevice实现,可满足真空计、离子泵、PLC等加速器装置中常用的串口,及以太网口智能设备的网络监控。整个控制系统实现了对加速器真空设备的远程采集、监测和真空阀门的联锁控制,保证束流的稳定运行。 相似文献
8.
9.
10.
11.
12.
13.
Tianjue Zhang Jianjun YangShizhong An Zhiguo Yin 《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》2011,269(24):2964-2967
This paper outlines the conceptual design work of a high power proton cyclotron proposed by the China Institute of Atomic Energy (CIAE) for a spallation neutron source, accelerator driven systems, production of radioactive ion beams, and other applications. For this cyclotron the 100 MeV injection proton beam is currently considered to be provided by the CYCIAE-100 cyclotron, which is under construction at CIAE and will be later replaced by a dedicated injector for beam upgrading. In order to minimize beam losses for high intensity operation, large turn separation at the extraction has first priority. After analyzing of different scenarios, including super conducting designs, a warm magnet solution was chosen. The conceptual design, field calculations, RF cavity simulations, etc. will be presented in the paper. 相似文献
14.
《Journal of Nuclear Science and Technology》2013,50(3):441-447
The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level radioactive solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former has cutting installations for large size wastes and the latter has melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750m3 and the volume reduction ratio is from 1.7 to 3.7. The WVRF has been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005. 相似文献
15.
21世纪近20年,我国高放废物深地质处置进入了一稳步发展的新阶段,在法律法规、技术标准、战略规划、选址和场址评价、工程屏障研究、处置库和地下实验室概念设计、核素迁移和安全评价研究等方面取得了显著进展。其主要亮点包括颁布了《中华人民共和国放射性污染防治法》和《中华人民共和国核安全法》,制定了《高放废物地质处置研究开发规划指南》,颁布了《高放废物地质处置设施选址》核安全导则,确定了2020年前开工建设地下实验室、2050年建成高放废物处置库的目标,甘肃北山预选区被确定为我国高放废物地质处置库首选预选区,建立了场址评价方法技术体系,确定了内蒙古高庙子膨润土为我国高放废物处置库的首选缓冲回填材料,建立了我国首台缓冲回填材料热 水-力-化学耦合条件下特性研究大型实验台架(China-Mock-Up),获得了一批关键放射性核素的迁移行为数据,开展了初步的安全评价,完成了地下实验室安全技术研究。确定甘肃北山的新场为我国高放废物地质处置地下实验室的场址。2019年5月6日,国家国防科工局批复中国北山高放废物地质处置地下实验室工程建设立项建议书,标志着我国高放废物地质处置正式进入地下实验室阶段。这一系列工作进展和取得的成绩为我国2020年开工建设地下实验室、掌握高放废物地质处置技术奠定了坚实的基础。 相似文献
16.
J.A. Snipes D. Beltran T. Casper Y. Gribov A. Isayama J. Lister S. Simrock G. Vayakis A. Winter Y. Yang L. Zabeo 《Fusion Engineering and Design》2012,87(12):1900-1906
The ITER Plasma Control System (PCS) requires an extensive set of about 50 diagnostic systems to measure the plasma response and about 20 actuators to act on the plasma to carry out its control functions. The specifications and real limitations of the actuators and diagnostics are being assessed as part of the ongoing conceptual design of the PCS to understand the potential impact on plasma control. The actuators include magnetic coils (central solenoid (CS), poloidal field (PF), vertical stability (VS), edge localized mode (ELM), correction coils (CC)), heating and current drive (electron cyclotron (EC), ion cyclotron (IC), neutral beam injection (NBI), and possibly lower hybrid (LH)), glow discharge cleaning, fueling and impurity gas and pellet injection, vacuum pumping, and disruption mitigation systems. Diagnostic systems are prioritized according to their role in machine protection (MP), basic control (BC), advanced control (AC), and physics studies (PS). At the conceptual design phase, detailed control algorithms do not yet need to be specified, but conceptual solutions must be chosen that satisfy the PCS requirements for control within the real constraints of the diagnostics and actuators. The feasibility of the chosen solutions must be proven either through established control schemes on existing machines or through an R&D program to develop them before they will be required on ITER. The diagnostic and actuator requirements of the PCS will evolve from first plasma through the high performance DT phase. A comparison is made of the expected requirements to control vertical stability, sawteeth, neoclassical tearing modes (NTMs), edge localized modes (ELMs), error fields, resistive wall modes (RWMs), Alfvén eigenmodes, and disruptions with the ITER baseline actuator and diagnostic specifications. 相似文献
17.
放射性血管支架制备研究进展 总被引:4,自引:0,他引:4
综述了用于预防PTCA后血管再狭窄的放射性血管支架的各种制备方法:同位素离子注入法、活化法及直接表面沉积或涂覆法的研究进展,分析了各种方法的特点,简述各种放射性支架的应用情况,并对发展趋势进行了评述。 相似文献
18.
19.
20.
A. G. Alekseev M. A. Gashev D. L. Londysh I. F. Malyshev I. M. Matora E. S. Mironov N. A. Monoszon L. M. Nemenov V. V. Pirogovskii N. A. Romanov N. S. Strel'tsov N. D. Fedorov 《Atomic Energy》1961,7(2):653-662
The basic data on a cyclotron with a pole-piece diameter of 120 cm are given. The arrangement of the principal parts of the system, the design features of the individual units, the radio frequency (rf) installation, the method of measuring and correcting the magnetic field, the features of the deflection system, and the method of focusing the beam on a remote target are all described. Deuterons are accelerated to an energy of 13.7 Mev in this machine. The use of a deflection system with focusing properties makes it possible to use magnetic quadruple lenses with small apertures which bring practically the entire deflected beam to a remote target. The parameters of the machine are such, that it will be possible to increase significantly theenergyof the accelerated ions in the future.The authors wish to thank E. G. Komar for valuable advice, F. K. Arkhangel'skii for great help in tests of the first cyclotron and D. G. Alkhazov for discussion of a number of problems connected with the design of the cyclotron. 相似文献