The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sci...The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). This paper reviews design and evolution of the WCCB blanket for CFETR, and presents a new WCCB blanket design according to the latest CFETR core parameters (major and minor radii are R = 7.2 m and a = 2.2 m, respectively) and missions. This new design is expected to satisfy multiple CFETR operation modes of 0.2, 0.5, 1.0, and 1.5 GW fusion power and achieve tritium self-sufficiency. The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics. Furthermore, the research and development (R&D) activities supporting to the WCCB blanket for CFETR are reported, including the design code, the water loop experiments, the pebble bed modeling and experiments, and the components fabrication technology.展开更多
The plasma current ramp-up is an important process for tokamak discharge,which directly affects the quality of the plasma and the system resources such as volt-second consumption and plasma current profile.The China F...The plasma current ramp-up is an important process for tokamak discharge,which directly affects the quality of the plasma and the system resources such as volt-second consumption and plasma current profile.The China Fusion Engineering Test Reactor(CFETR)ramp-up discharge is predicted with the tokamak simulation code(TSC).The main plasma parameters,the plasma configuration evolution and coil current evolution are given out.At the same time,the volt-second consumption during CFETR ramp-up is analyzed for different plasma shaping times and different plasma current ramp rates dIP/dt with/without assisted heating.The results show that the earlier shaping time and the faster plasma current ramp rate with auxiliary heating will enable the volt-second to save 5%-10%.At the same time,the system ability to provide the volt-second is probably 470 V·s.These simulations will give some reference to engineering design for CFETR to some degree.展开更多
针对CFETR(China Fusion Engineering Test Reactor)设计面临的文档管理需求,提出一种基于依赖管理的CFETR文档管理系统。CFETR文档管理系统由基础文档管理模块和设计包管理模块组成。其中,基础文档管理模块用来管理原始的设计文档。考...针对CFETR(China Fusion Engineering Test Reactor)设计面临的文档管理需求,提出一种基于依赖管理的CFETR文档管理系统。CFETR文档管理系统由基础文档管理模块和设计包管理模块组成。其中,基础文档管理模块用来管理原始的设计文档。考虑到原始数据的安全性、稳定性需求,基础文档管理模块基于成熟的商业软件ENOVIA开发。设计包管理模块解决设计文档的依赖问题。基于"设计包"的概念,定义设计包的数据结构,并在数据库系统中实现设计包的持久化存储。开发设计包管理程序,其具备创建、审批、查看和销毁设计包的功能。提出依赖冲突检测算法,能够识别版本依赖冲突和循环依赖冲突。经过部署和测试,该系统能有效地管理文档和设计包依赖关系,从而保障设计工作的自洽性,提高设计效率。展开更多
基金the financial support of the National Key R&D Program of China(Grants2017YFE0300503 and 2017YFE0300604)the National Natural Science Foundation of China(Grant 11775256)
文摘The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). This paper reviews design and evolution of the WCCB blanket for CFETR, and presents a new WCCB blanket design according to the latest CFETR core parameters (major and minor radii are R = 7.2 m and a = 2.2 m, respectively) and missions. This new design is expected to satisfy multiple CFETR operation modes of 0.2, 0.5, 1.0, and 1.5 GW fusion power and achieve tritium self-sufficiency. The feasibility of the updated blanket design is evaluated from the aspects of neutronics and thermo-hydraulics. Furthermore, the research and development (R&D) activities supporting to the WCCB blanket for CFETR are reported, including the design code, the water loop experiments, the pebble bed modeling and experiments, and the components fabrication technology.
基金Project supported by the National Key Research and Development Program of China(Grant Nos.2017YFE0300500 and 2017YFE0300501)the National Natural Science Foundation of China(Grant Nos.11875290 and 11875253)the Fundamental Research Funds for the Central Universities of China(Grant No.WK3420000004).
文摘The plasma current ramp-up is an important process for tokamak discharge,which directly affects the quality of the plasma and the system resources such as volt-second consumption and plasma current profile.The China Fusion Engineering Test Reactor(CFETR)ramp-up discharge is predicted with the tokamak simulation code(TSC).The main plasma parameters,the plasma configuration evolution and coil current evolution are given out.At the same time,the volt-second consumption during CFETR ramp-up is analyzed for different plasma shaping times and different plasma current ramp rates dIP/dt with/without assisted heating.The results show that the earlier shaping time and the faster plasma current ramp rate with auxiliary heating will enable the volt-second to save 5%-10%.At the same time,the system ability to provide the volt-second is probably 470 V·s.These simulations will give some reference to engineering design for CFETR to some degree.
文摘针对CFETR(China Fusion Engineering Test Reactor)设计面临的文档管理需求,提出一种基于依赖管理的CFETR文档管理系统。CFETR文档管理系统由基础文档管理模块和设计包管理模块组成。其中,基础文档管理模块用来管理原始的设计文档。考虑到原始数据的安全性、稳定性需求,基础文档管理模块基于成熟的商业软件ENOVIA开发。设计包管理模块解决设计文档的依赖问题。基于"设计包"的概念,定义设计包的数据结构,并在数据库系统中实现设计包的持久化存储。开发设计包管理程序,其具备创建、审批、查看和销毁设计包的功能。提出依赖冲突检测算法,能够识别版本依赖冲突和循环依赖冲突。经过部署和测试,该系统能有效地管理文档和设计包依赖关系,从而保障设计工作的自洽性,提高设计效率。
