基于CODAC的ITER电流引线测控系统  

Monitor and control system of the current lead for ITER based on CODAC framework

作　　者：朱胜本 丁开忠[1] 杜庆庆[1] 冯汉升[1] 陆坤[1] 刘承连[1] 宋云涛[1] 

机构地区：[1]中国科学院等离子体物理研究所,合肥230031

出　　处：《核技术》2015年第10期59-64,共6页Nuclear Techniques

摘　　要：中国科学院等离子体物理研究所(Institute of Plasma Physical,Chinese Academy of Sciences,ASIPP)负责国际热核聚变实验堆(International Thermonuclear Experimental,ITER)60根高温超导电流引线(High Temperature Superconducting Current Lead,HTSCL)产品的研制与测试,并在2013–2015年间开展了三对三种电流等级(68 k A、55 k A和10 k A)的高温超导电流引线认证制造。为检验电流引线的低温大电流性能,ASIPP与印度塔塔咨询服务公司(Tata Consultancy Service,TCS)及ITER合作开发了基于CODAC(Control,Data Access and Communication)框架的ITER高温超导电流引线测控系统。该系统包括传统西门子PLC300工艺过程测控系统、基于Lab VIEW的失超保护系统、基于PLC400冗余设计的互锁系统和基于NI c系列模块的快速控制系统(Plant system Controller,Fast Controls,PCF)。目前本系统已通过三轮验收测试并在2015年1月份的ITER CC 10 k A电流引线原型件和同年7月份的ITER TF 68 k A电流引线原型件中成功应用。结果表明,本系统能很好地满足电流引线的实验需求,得到ITER国际认同。电流引线测控系统软硬件遵照ITER的CODAC标准进行设计,是CODAC和互锁保护规范的首次在ITER真实组件物理性能测试的联合应用案例,可作为ITER采购包出厂验收推行的CODAC模范。Background： Institute of Plasma Physics, Chinese Academy of Sciences （ASIPP） is cooperating with India＇s Tata Consultancy Services （TCS） and International Thermonuclear Experimental （ITER） to build a new measurement and control system engineering for high temperature superconducting current lead （HTSCL） under the framework of CODAC （Control, Data Access and Communication）. Purpose： This study aims to design a data acquisition and control system for this project that was implemented according to the requirements of CODAC system. Methods： It contains the fast controller, the conventional Programmable Logic Controller （PLC） system, i.e. the Siemens 300 series and 400 series PLC, is applied for slow controller and data acquisition sub-system, interlock sub-system using the integrated module of CODAC. Fast controller and quench detection sub-system were implemented by using National Instruments （NI）’s NI PXIe-6259, NI 9219, etc. modules and the LabVIEW programming with embedded Experimental Physics and Industrial Control System （EPICS） interface. Each subsystem is developed and applied by following the framework standard of ITER CODAC. Results： This proposed system has passed the second round of testing, showing that it full fills the experimental requirements of HTSCL test. Conclusion： The measurement and control system of HTSCL was designed completely in accordance with of ITER CODAC standard, it follows strictly the CODAC specification of ASIPP and ITER international organization. Most importantly, it’s the first time to combine CODAC and interlock protection system of ITER for real physical performance test, it can be used as a model of CODAC norms in the future.

关 键 词：国际热核聚变实验堆 高温超导电流引线 CODAC 测控系统 EPICS 

分 类 号：TL67[核科学技术—核技术及应用]