偏滤器物理设计与实验研究

应用B2-code模拟了偏滤器等离子体行为,优化了HL-2A装置偏滤器位形。研究了偏滤器刮削层中等离子体与器壁间过渡鞘层的离子碰撞效应,模拟研究了利用LHCD和NBI控制等离子体剖面分布在HL-2A中建立准稳态的反磁剪切位形。HL-2A装置首次实现了下单零点的偏滤器位形运行,完成了偏滤器初步物理实验,截至2004年底,获得等离子体电流320 kA,等离子体存在时间1 580 ms,环向磁场2.2 T。开展了高功率密度聚变堆偏滤器靶板的设计研究,特别是流动液态锂偏滤器靶板表面的物理过程的研究。探索性研究了用RF有质动力势改善偏滤器排灰效率和减少氚投料量。对FEB- E聚变堆偏滤器进行了优化设计。用电子束模拟对碳基材料及钨进行了高热负荷冲击实验,完成了钨/铜合金的热等静压焊接及热疲劳试验研究。研究了氦在钨中的滞留与热解吸行为。     

HL-2A磁面位形的计算机绘图软件包的开发与研制

HL-2A是在原德国ASDEX基础上改进的大型托卡马克装置,该装置带有上下两组偏滤器线圈。从目前的HL-2A的改进方案看,其几何尺寸、磁场位形和物理参数大体和ASDEX相似,只是环向磁场、等离子体电流及拉长比稍有不同。由于未来的HL-2A装置上带有偏滤器,而我们以前的位形计算大多在没有偏滤器位形的HL-1及HL-1M上进行的,所以开展有关HL-2A位形的物理研究及相关的数值计算和程序设计是很重要的工作。     

HL-2A托卡马克装置的工程和实验概况

中国环流器二号A装置(HL-2A)是核工业西南物理研究院2002年投入实验运行的托卡马克,它是我国第1个具有偏滤器、等离子体截面具有一定垂直拉长的托卡马克.HL-2A的磁体使用铜导体,具有良好的灵活性和等离子体的可近性,其极向场线圈全部位于环向场线圈之内,位于真空室内的偏滤器的成形线圈可建立双零和单零的偏滤器位形.HL-2A已发展了30多套先进的等离子体诊断系统和总功率4 MW的辅助加热系统,加料技术得到持续发展.随着上述系统的建设和放电综合控制技术的提高,HL-2A装置已获得了高约束模式,这为开展先进托卡马克(AT)物理实验,ITER和聚变堆的科学、技术和工程问题等的研究奠定了基础.HL-2A也成为国际上最活跃的中型托卡马克,为国际托卡马克物理活动(ITPA)作出了积极贡献.     

中国环流器二号A装置工程与实验进展

介绍了中国环流器二号A(简称HL-2A)装置上关键聚变工程技术取得的新进展及在磁约束聚变科学若干关键课题研究取得的重要实验成果,特别是在HL-2A装置上成功实现了偏滤器位形下具有边缘局域模的高约束模式运行,是我国磁约束聚变实验研究史上具有里程碑意义的重大进展,使我国的磁约束聚变科学和等离子体物理实验研究进入了一个崭新的阶段。     

中国环流器二号A装置工程与实验进展

介绍了中国环流器二号A(简称HL-2A)装置上关键聚变工程技术取得的新进展及在磁约束聚变科学若干关键课题研究取得的重要实验成果,特别是在HL-2A装置上成功实现了偏滤器位形下具有边缘局域模的高约束模式运行,是我国磁约束聚变实验研究史上具有里程碑意义的重大进展,使我国的磁约束聚变科学和等离子体物理实验研究进入了一个崭新的阶段。     

HL-2A中多路分时积分器的研制

中国环流器二号 A 装置(HL-2A)是我国第-个具有偏滤器位形的托卡马克装置,利用其极向偏滤器在高参数等离子体条件下开展与偏滤器位形运行有关的研究.直观的观测核放射过程中核脉冲信号随放射时间的强弱变化规律对于掌握受控核聚变有着重大的意义.我们为HL-2A装置研制的多路分时积分器具有自动削掉输入信号的负向反脉冲,积分时间0.2～1 ms五档可调,统一起始TTL触发脉冲,20 s自动定时工作,同时有十路信号积分的特点.     

中国聚变工程实验堆雪花偏滤器脱靶运行的SOLPS模拟

在中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)的工程概念设计中,为探索有效降低偏滤器靶板热负荷的途径,相对于国际热核聚变实验堆(International Thermonuclear Experimental Reactor,ITER)特别增加了两个极向场线圈用于产生近年来新提出的雪花偏滤器位形。脱靶运行状态下,偏滤器靶板上的热负荷显著降低,但同时由于偏滤器温度的降低,杂质约束性能会变差,因此需要对CFETR雪花偏滤器的脱靶运行状态进行研究。基于边界等离子体物理模拟软件SOLPS(Scrape-off Layer Plasma Simulation),通过数值模拟研究了CFETR雪花偏滤器的脱靶运行状态。模拟中通过主等离子体室内的D2充气改变等离子体密度。当充气速度足够高时,CFETR雪花偏滤器实现完全脱靶,靶板上的离子流和热负荷都显著降低。但此时偏滤器区域等离子体温度已经非常低,杂质将容易通过X点进入芯部,有产生辐射不稳定性的风险。因此,对于CFETR雪花偏滤器较为合适的工作状态应当是部分脱靶运行。     

HL-2A中基于USB新型多路分时定标器的研制

中国环流器二号A(HL-2A)装置是我国第一个具有偏滤器位形的托卡马克装置.掌握聚变等离子体随时间的变化规律对实现受控核聚变有十分重大的意义,HL-2A在新一轮改建中对电子学探测提出了更高、更快的要求.为HL-2A研制的USB新型多路分时定标器具有USB接口和PC图形化操作界面,可同时定标5路以上信号,分时间隔2-50 ms可选,计数率达2 MHz以上,一次可获取放电后20 s内所有信息,并给出离线后的数据分析与图形显示.     

STE—2反场箍缩极向偏滤器实验的首批结果

已在有一个外偏滤器室的放电容器中产生了有单极向零的反场箍缩。在目前的实验中没有装上导电壳。极向偏滤器位形维持的时间为壁的时间常数，在磁起伏中ｍ＝１撕裂模的优势不受偏滤器位形的影响。采用偏滤器位形和在偏滤器电流达到主等离子体电流的３０％的情况下，极向偏滤器都没有引起对等离子体性能的有害效应。     

FEB混合堆偏滤器的物理研究

描述FEB偏滤器的物理设计研究。在工程概要设计(FEB-E)阶段,偏滤器的结构从开式优化为闭式,以改善偏滤器的杂质控制和增强原子损失过程。偏滤器运行在喷气和注杂组合下的脱靶等离子体或部分脱靶等离子体模式(Partial Detached Plasma Mode)。硼被选为注入杂质。应用改进了的NEWT1D编码模拟了喷气和注杂下删削层/偏滤器中等离子体及杂质的输运。着眼于杂质居留和杂质辐射,优化了喷气口的位置。在辐射偏滤器概念下,应用两点输运编码和杂质辐射模型估算了等离子体压力。计算表明:偏滤器靶前等离子体压降系数f_p不仅和辐射份额f_(rad)有关,而且和删削层驻点密度n_s密切相关。     

Magnetic configuration flexibility of snowflake divertor for HL-2M

HL-2M (Li, 2013 [1]) is a tokamak device that is under construction. Based on the magnetic coils design of HL-2M, four kinds of divertor configurations are calculated by CORSICA code (Pearlstein et al., 2001 [2]) with the same main plasma parameters, which are standard divertor, exact snowflake divertor, snowflake-plus divertor and snowflake-minus divertor configurations. The potential properties of these divertors are analyzed and presented in this paper: low poloidal field area around X-point, connection length from outside mid-plane to the primary X-point, target plate design and magnetic field shear. The results show that the snowflake configurations not only can reduce the heat load at divertor target plates, but also may improve the magneto-hydrodynamic stability by stronger magnetic shear at the edge. A new divertor configuration, named “tripod divertor”, is designed by adjusting the positions of the two X-points according to plasma parameters and magnetic coils current of HL-2M.     

Impurity Measured by VUV Spectrometer and OMA on HL-2A Tokamak

Impurity is one of the key issues on a great impact to the quality of tokamak plasma.HL-2A is the first divertor tokamak in China. In this paper the experimental results are presented on impurity through the line emission measurement in the campaign in 2003 under the limiter and divertor configurations. The low-Z impurities such as carbon and oxygen are the most important components in the plasma, but their content are not so high to affect the discharge quality. The high-Z impurities such as copper and ferrum are not essential. The emission intensity of impurity is clearly decreased during the divertor configuration formed.     

Numerical Simulation and Experimental Identification of Divertor Configuration in the HL-2A Tokamak

Single- and double-null divertor configurations in HL-2A are simulated by SWEQU equilibrium code. Lower divertor discharges in the first physics campaign have been achieved by two kinds of power supply method of multipole-field coils. Single-null divertor configuration has been identified by visible photography, target probe arrays and the reconstructed magnetic surface. Magnetic separatrix and minor radius of plasma column are obtained by a reconstructed code of multiple current filaments using 18 Mirnov signals.     

HL-2A Tokamak Edge Modeling with B2

The outer divertor plasma of HL-2A and its associated scrape-off plasma have been simulated using a two-dimensional multi-species fluid code of Braams with a simplified neutral gas model. HL-2A has a double-null closed divertor in separate divertor chambers above and below the nearly circular plasma tours. The computed numerical grid is developed according to an ideal magnetic surface. The calculation is involved only with pure hydrogen plasma. The emphasis has been focused on parametric studies involving variation of the assumptions made for the core plasma. The peak temperatures and the heat flux near the target are of the principal concern。     

Functions of intrinsic magnetic field line structures on lithium ion transport in the LHD plasma periphery

Plasma discharge operation with lithium coating suggests that the lithium effectively control neutral particles in the plasma periphery, which can lead to improvement of plasma parameters. The effect of lithium coating on the large helical device (LHD) for a closed helical divertor configuration is discussed from viewpoints of neutral particle and impurity ion transport in the plasma periphery. It shows that the closed helical divertor configuration can enhance the neutral particle density in the divertor region, which is enough to achieve efficient particle control, and that it can effectively confine neutral lithium atoms near divertor plates. A one-dimensional impurity (lithium) ion transport analysis along magnetic field lines on divertor legs indicates that the friction force due to the plasma flow from the main plasma is dominant over the thermal force caused by the temperature gradient on the divertor legs, which prevents lithium ion contamination in the main plasma and excessive cooling of the plasma temperature in an ergodic layer. The analysis shows that the lithium coating is compatible with LHD plasma discharge operation for the closed helical divertor configuration.     

Vacuum System for HL-2A Tokamak

The vacuum system for HL-2A was built in 2003. The test results indicated that this system is feasible. It consists of three main parts: a pumping system, a pumping divertor and a glow discharge cleaning (GDC) system. For the pumping system, there are three main functions: (1) evacuating the vacuum vessel thus to produce an ultra high vacuum, (2) removal of impurities released during baking and (3) pumping during GDC. The pumping divertor controls the particles at the plasma edge and the GDC system provides a clean wall conditioning. During the first campaign of physical trial experiment on HL-2A, the ultimate pressure reached 4.6 × 10-6 Pa, and the total leakage and outgassing rate in 12 hours was 1.8 × 10-5 Pa·m3/s, which is close to that of ASDEX.     

Impurity Measurement and Study on HL-2A Divertor Tokamak

HL-2A tokamak with two close divertors has been operated since 2003. In the experimental campaign of 2004 the divertor configuration has been successfully formed and the sillconization as a wall conditioning has been firstly done in this device. The divertor configuration can be reconstructed by the CFc code. Impurity behavior has been investigated during the experiment with divertor configuration and wall conditioning. The reduction of impurity is clear under both conditions of divertor configuration and siliconization.     

Thermal-hydraulic analysis of the HL-2M divertor using an homogeneous equilibrium model

The heat flux of the HL-2M divertor would reach 10 MWm-2 or more at the local area when the device operates at high parameters.Subcooled boiling could occur at high thermal load,which would be simulated based on the homogeneous equilibrium model.The results show that the current design of the HL-2M divertor could withstand the local heat flux 10 MW m-2 at a plasma pulse duration of 5 s,inlet coolant pressure of 1.5 MPa and flow velocity of 4 m s-1.The pulse duration that the HL-2M divertor could withstand is closely related to the coolant velocity.In addition,at the time of 2 min after plasma discharge,the flow velocity decreased from 4 m s-1 to 1 m s-1,and the divertor could also be cooled to the initial temperature before the next plasma discharge commences.