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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。
The Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) is responsible for 60 High Temperature Superconducting Current Lead (HTSCL) tests of the International Thermonuclear Experimental Station (ITER) Product development and testing. In 2013-2015, three pairs of high current superconducting current leads certified for three current ratings (68 kA, 55 kA and 10 kA) were manufactured. To test the low-temperature and high-current performance of current leads, ASIPP partnered with Tata Consultancy Service (TCS) and ITER to develop an ITER high temperature superconducting current lead measurement and control system based on the CODAC (Control, Data Access and Communication) framework . The system includes the traditional Siemens PLC300 process monitoring and control system, the Lab VIEW-based quench protection system, the interlocking system based on the PLC400 redundancy design and the NI c series module based rapid control system (PCF). At present, the system has passed three rounds of acceptance tests and was successfully applied in ITER CC 10 k A current lead prototypes in January 2015 and ITER TF 68 k A current lead prototypes in July of the same year. The results show that the system can meet the experimental requirements of current lead well and get the international recognition of ITER. The current and lead measurement and control system hardware and software are designed according to ITER’s CODAC standard. It is the first time that CODAC and interlock protection specifications are applied to the physical performance test of ITER real components and can be used as the CODAC model for ITER purchase package acceptance.