Tokamak plasmas with elongated cross sections are susceptible to vertical displacement events(VDEs),which can damage the first wall via heat flux or electromagnetic(EM)forces.We present a 3D nonlinear reduced magnetoh...Tokamak plasmas with elongated cross sections are susceptible to vertical displacement events(VDEs),which can damage the first wall via heat flux or electromagnetic(EM)forces.We present a 3D nonlinear reduced magnetohydrodynamic(MHD)simulation of CFETR plasma during a cold VDE following the thermal quench,focusing on the relationship among the EM force,plasma displacement,and the n=1 mode.The dominant mode,identified as m/n=2/1,becomes destabilized when most of the current is contracted within the q=2 surface.The displacement of the plasma current centroid is less than that of the magnetic axis due to the presence of SOL current in the open field line region.Hence,the symmetric component of the induced vacuum vessel current is significantly mitigated.The direction of the sideways force keeps a constant phase approximately compared to the asymmetric component of the vacuum vessel current and the SOL current,which in turn keep in-phase with the dominant 2/1 mode.Their amplitudes are also closely associated with the growth of the dominant mode.These findings provide insights into potential methods for controlling the phase and amplitude of sideways forces during VDEs in the future.展开更多
The supercritical CO_(2)cOoled Lithium-Lead(COOL)blanket has been designed as one advanced blanket candidate for the Chinese Fusion Engineering Test Reactor(CFETR).This work focuses on the electromagnetic(EM)loads(Max...The supercritical CO_(2)cOoled Lithium-Lead(COOL)blanket has been designed as one advanced blanket candidate for the Chinese Fusion Engineering Test Reactor(CFETR).This work focuses on the electromagnetic(EM)loads(Maxwell force and Lorentz force)acting on the COOL blanket,which are important mechanical loads in further structural analysis of the COOL blanket.A 3D electromagnetic analysis is performed using the ANSYS finite element method to obtain EM loads on the COOL blanket in this study.At first,the magnetic scalar potential(MSP)method is used to obtain the magnetic field and the Maxwell force on the COOL blanket.Then,the magnetic vector potential(MVP)method is performed during a plasma disruption event to get the eddy current distribution.At last,a multi-step method is adopted for the calculation of the Lorentz force and the torque.The maximum Lorentz forces of inboard and outboard blanket structural components are 5624 kN and 2360 kN respectively.展开更多
为解决核聚变发电热功率输出不稳定性和汽轮发电机组平稳运行之间的矛盾,中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)核聚变发电厂可运用储热技术对核聚变堆的功率输出进行削峰平谷。储热技术有多种类型,各类储...为解决核聚变发电热功率输出不稳定性和汽轮发电机组平稳运行之间的矛盾,中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)核聚变发电厂可运用储热技术对核聚变堆的功率输出进行削峰平谷。储热技术有多种类型,各类储热技术对于核聚变发电厂的适用性亟须进行对比。本文选取核聚变反应堆氦冷陶瓷增殖包层的参数作为储热技术边界条件,通过对储热技术适用温度范围进行评估,初步分析出有潜力运用于CFETR核聚变发电厂的三种储热技术,并对其进行成本初步预测。三大类储热技术均可选出适用CFETR核聚变发电厂氦冷增殖包层温度参数的储热介质。但化学储热由于其吸热和放热存在温差,不利于系统的稳定性及造成能量的损耗,显热储热技术和相变储热技术吸热温度和放热温度温差较小,具有应用于CFETR核聚变发电厂的潜力。初步经济性分析结果显示:相变储热成本最低,其次为熔融盐储热,再次为固相显热储热技术中利用硅砖作为储热介质,固相显热储热技术中利用铸钢作为储热介质成本最高。储热技术中,熔融盐储热技术、相变储热技术、固相显热储热具有应用于核聚变发电厂氦冷增殖包层的先决条件。熔融盐储热技术成熟度较高,有大量工程应用,造价在相变储热和固相显热储热之间,运用潜力较大。相变储热的成本最低,参数适用于核聚变发电,但其技术成熟度较低,有望成为未来研究的重点。展开更多
The investigation of electron cyclotron(EC)wave absorption and current drive has been performed for the China Fusion Engineering Test Reactor(CFETR)hybrid scenarios using the TORAY code.To achieve the physics goal of ...The investigation of electron cyclotron(EC)wave absorption and current drive has been performed for the China Fusion Engineering Test Reactor(CFETR)hybrid scenarios using the TORAY code.To achieve the physics goal of the EC system in CFETR,a total of four wave frequency values and nine locations of launching antennas have been considered,and the injection poloidal and toroidal angles have been scanned systematically.The electron cyclotron current drive(ECCD)efficiency of the 170 GHz EC system is quite low due to the wave-particle interactions being located at the low-field side.To optimize the ECCD efficiency,the wave frequency is increased up to 221–250 GHz,which leads to the power being deposited at the high-field side.The off-axis ECCD efficiency can be significantly enhanced by launching EC waves from the top window and injecting them towards the high-field side.The optimized ECCD efficiency atρ=0.32 and atρ=0.4 is 2.9 and 2.2 times that of 170 GHz,respectively.展开更多
China Fusion Engineering Test Reactor(CFETR)is China's self-designed and ongoing next-generation fusion reactor project.Tritium confinement systems in CFETR guarantee that the radiation level remains below the saf...China Fusion Engineering Test Reactor(CFETR)is China's self-designed and ongoing next-generation fusion reactor project.Tritium confinement systems in CFETR guarantee that the radiation level remains below the safety limit during tritium handling and operation in the fuel cycle system.Our tritium technology team is responsible for studying tritium transport behavior in the CFETR tritium safety confinement systems of the National Key R&D Program of China launched in 2017,and we are conducting CFETR tritium plant safety analysis by using CFD software.In this paper,the tritium migration and removal behavior were studied under a postulated accident condition for the Tokamak Exhaust Processing system of CFETR.The quantitative results of the transport behavior of tritium in the process room and glove box during the whole accident sequence(e.g.,tritium release,alarm,isolation,and tritium removal)have been presented.The results support the detailed design and engineering demonstration-related research of CFETR tritium plant.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supported by the National MCF Energy R&D Program of China(Grant Nos.2019YFE03010001 and 2018YFE0311300).
文摘Tokamak plasmas with elongated cross sections are susceptible to vertical displacement events(VDEs),which can damage the first wall via heat flux or electromagnetic(EM)forces.We present a 3D nonlinear reduced magnetohydrodynamic(MHD)simulation of CFETR plasma during a cold VDE following the thermal quench,focusing on the relationship among the EM force,plasma displacement,and the n=1 mode.The dominant mode,identified as m/n=2/1,becomes destabilized when most of the current is contracted within the q=2 surface.The displacement of the plasma current centroid is less than that of the magnetic axis due to the presence of SOL current in the open field line region.Hence,the symmetric component of the induced vacuum vessel current is significantly mitigated.The direction of the sideways force keeps a constant phase approximately compared to the asymmetric component of the vacuum vessel current and the SOL current,which in turn keep in-phase with the dominant 2/1 mode.Their amplitudes are also closely associated with the growth of the dominant mode.These findings provide insights into potential methods for controlling the phase and amplitude of sideways forces during VDEs in the future.
基金supported by the Comprehensive Research Facility for Fusion Technology(CRAFT)Program of China(No.2018-000052-73-01-001228)National Natural Science Foundation of China(No.12205330)。
文摘The supercritical CO_(2)cOoled Lithium-Lead(COOL)blanket has been designed as one advanced blanket candidate for the Chinese Fusion Engineering Test Reactor(CFETR).This work focuses on the electromagnetic(EM)loads(Maxwell force and Lorentz force)acting on the COOL blanket,which are important mechanical loads in further structural analysis of the COOL blanket.A 3D electromagnetic analysis is performed using the ANSYS finite element method to obtain EM loads on the COOL blanket in this study.At first,the magnetic scalar potential(MSP)method is used to obtain the magnetic field and the Maxwell force on the COOL blanket.Then,the magnetic vector potential(MVP)method is performed during a plasma disruption event to get the eddy current distribution.At last,a multi-step method is adopted for the calculation of the Lorentz force and the torque.The maximum Lorentz forces of inboard and outboard blanket structural components are 5624 kN and 2360 kN respectively.
文摘为解决核聚变发电热功率输出不稳定性和汽轮发电机组平稳运行之间的矛盾,中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)核聚变发电厂可运用储热技术对核聚变堆的功率输出进行削峰平谷。储热技术有多种类型,各类储热技术对于核聚变发电厂的适用性亟须进行对比。本文选取核聚变反应堆氦冷陶瓷增殖包层的参数作为储热技术边界条件,通过对储热技术适用温度范围进行评估,初步分析出有潜力运用于CFETR核聚变发电厂的三种储热技术,并对其进行成本初步预测。三大类储热技术均可选出适用CFETR核聚变发电厂氦冷增殖包层温度参数的储热介质。但化学储热由于其吸热和放热存在温差,不利于系统的稳定性及造成能量的损耗,显热储热技术和相变储热技术吸热温度和放热温度温差较小,具有应用于CFETR核聚变发电厂的潜力。初步经济性分析结果显示:相变储热成本最低,其次为熔融盐储热,再次为固相显热储热技术中利用硅砖作为储热介质,固相显热储热技术中利用铸钢作为储热介质成本最高。储热技术中,熔融盐储热技术、相变储热技术、固相显热储热具有应用于核聚变发电厂氦冷增殖包层的先决条件。熔融盐储热技术成熟度较高,有大量工程应用,造价在相变储热和固相显热储热之间,运用潜力较大。相变储热的成本最低,参数适用于核聚变发电,但其技术成熟度较低,有望成为未来研究的重点。
基金supported by the National Key R&D Program of China(Nos.2017YFE0300500 and 2017YFE0300503)the Comprehensive Research Facility for Fusion Technology Program of China(No.2018-000052-73-01-001228).
文摘The investigation of electron cyclotron(EC)wave absorption and current drive has been performed for the China Fusion Engineering Test Reactor(CFETR)hybrid scenarios using the TORAY code.To achieve the physics goal of the EC system in CFETR,a total of four wave frequency values and nine locations of launching antennas have been considered,and the injection poloidal and toroidal angles have been scanned systematically.The electron cyclotron current drive(ECCD)efficiency of the 170 GHz EC system is quite low due to the wave-particle interactions being located at the low-field side.To optimize the ECCD efficiency,the wave frequency is increased up to 221–250 GHz,which leads to the power being deposited at the high-field side.The off-axis ECCD efficiency can be significantly enhanced by launching EC waves from the top window and injecting them towards the high-field side.The optimized ECCD efficiency atρ=0.32 and atρ=0.4 is 2.9 and 2.2 times that of 170 GHz,respectively.
基金the National Key R&D Program of China-National Magnetic Confinement Fusion Science Program(No.2017YFE0300305).
文摘China Fusion Engineering Test Reactor(CFETR)is China's self-designed and ongoing next-generation fusion reactor project.Tritium confinement systems in CFETR guarantee that the radiation level remains below the safety limit during tritium handling and operation in the fuel cycle system.Our tritium technology team is responsible for studying tritium transport behavior in the CFETR tritium safety confinement systems of the National Key R&D Program of China launched in 2017,and we are conducting CFETR tritium plant safety analysis by using CFD software.In this paper,the tritium migration and removal behavior were studied under a postulated accident condition for the Tokamak Exhaust Processing system of CFETR.The quantitative results of the transport behavior of tritium in the process room and glove box during the whole accident sequence(e.g.,tritium release,alarm,isolation,and tritium removal)have been presented.The results support the detailed design and engineering demonstration-related research of CFETR tritium plant.
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。
