Numerical and Experimental Evaluation of Shine-Through Loss and Beam Heating Due to Neutral Beam Injection on EAST

This research applies experimental measurements and NUBEAM,ONETWO and TRANSP modules to investigate the shine-through(ST)loss ratio and beam heating percentage of neutral beam injection on EAST.Measurements and simulations confirm that the ST loss ratio increases linearly with beam energy,and decreases exponentially with plasma density.Moreover,using the multi-step fitting method,we present analytical quantitative expressions of ST loss ratio and beam heating percentage,which are valuable for the high parameter long-pulse experiments of EAST.

Simulations of Neutral Beam Ion Ripple Loss on EAST

Predictions on the ripple loss of neutral beam fast ions on EAST are investigated with a guiding center code, including both ripple and collisional effects. A 6% to 16% loss of neutral beam ions is predicted for typical EAST experiments, and a synergistic enhancement of fast ion loss is found for toroidal field （TF） ripples with collisions. The lost ions are strongly localized and will cause a maximum heat load of - 0.05 MW/m^2 on the first wall.

Conceptual Design of Neutral Beam Injection System for EAST

Neutral beam injection （NBI） system with two neutral beam injections will be con- structed on the Experimental Advanced Superconducting Tokamak （EAST） in two stages for high power auxiliary plasmas heating and non-inductive current drive. Each NBI can deliver 2-4 MW beam power with 50-80 keV beam energy in 10-100 s pulse length. Each elements of the NBI system are presented in this contribution.

Analysis of the Pipe Heat Loss of the Water Flow Calorimetry System in EAST Neutral Beam Injector

Neutral beam injection heating is one of the main auxiliary heating methods in controllable nuclear fusion research. In the EAST neutral beam injector, a water flow calorimetry （WFC） system is applied to measure the heat load on the electrode system of the ion source and the heat loading components of the beamline. Due to the heat loss in the return water pipe, there are some measuring errors for the current WFC system. In this paper, the errors were measured experimentally and analyzed theoretically, which lay a basis for the exact calculation of beam power deposition distribution and neutralization efficiency.

Studies of beam ion confinement to enhance plasma performance on EAST

A key physics issue for achieving steady-state high-performance plasmas on EAST tokamak is to decrease beam-ion losses to improve plasma confinement during neutral beam injections(NBIs).To decrease the beam losses,previous counter-I_(p)NBI injections are upgraded to co-I_(p)injections.Analysis shows that due to the reversed direction of drift across the flux surfaces caused by the pitch angle,the beam prompt loss fraction decreases from about 49%to 3%after the upgrade.Moreover,because of the change of entire beam path,beam shine-through(ST)loss fraction for counter-I_(p)tangential and counter-I_(p)perpendicular injections is reversed to co-I_(p)tangential and co-I_(p)perpendicular injections,respectively.Due to the change in the initial trapped-confined beam ion fraction caused by the peaked pitch profiles,the losses induced by toroidal ripple field are also reversed after the upgrade.To further improve the beam-ion confinement under the present NBI layout,the amplitudes of toroidal field are increased from 1.75 to 2.20 T.Result shows that,due to the smaller orbit width and peaked pitch angle profile,the beam prompt loss power is lower with higher toroidal field.Due to the synergy of higher initial trapped-confined beam ion fraction and narrower Goldston-White-Boozer(GWB)boundary,the loss induced by ripple diffusion is higher with higher toroidal field.The combined effect of beam ST loss,prompt loss and ripple loss,contributes to the increase in beam ion density.The decrease in beam loss power enhances beam heating efficiency,especially the fraction of beam heating ions.Finally,comparison between simulation and measurement by^(235)U fission chamber(FC)indicates that the increase in neutron rate is mainly contributed by improvement of beam-ion confinement.This study can provide potential support for beam operation and high-T_(i)experiment on EAST tokamak.

Development of Distributed Control System for Neutral Beam Injector on EAST

A distributed control system of Neutral Beam Injector （NBI） on the Experimental Advanced Superconducting Tokamak （EAST-NBI） is briefly presented in this paper. The control system is developed in accordance with the experimental operational characteristics of the EAST- NBI. The NBI control system （NBICS）, which is based on the computer network technologies and classified according to the control levels, consists of three levels： a remote monitoring layer, a server control layer, and a field control layer. The 3-layer architecture is capable of extending the system functions and upgrading devices. The timing system provides the reference clock of the synchronization and interlock for the EAST-NBI system. An interlock system ensures the safety of the experiment operators and field devices. Both of the ion sources of the beamline are designed to operate independently. This lays an important foundation for developing a control system for the second beamline on EAST. Experimental results demonstrate that the NBICS meets functional requirements of the EAST-NBI control, and makes experimental operations visual and automatic.

Overview of Development Status for EAST-NBI System

The neutral beam injection （NBI） system was developed on the Experimental Ad- vanced Superconducting Tokamak （EAST） for plasma heating and current driving. This paper presents the brief history, design, development, and the main experimental results of the R＆D of neutral beam injector on the test bed and on EAST. In particular, it will describe： （1） how the two beamlines with a total beam power of 8 MW were developed; （2） the design of the EAST-NBI system including the high power ion source, main vacuum chamber, inner components, beam diag- nostic system and sub-system; （3） the experimental results of beamline-1 on the summer campaign of EAST in 2014 and, （4） the status of beamline-2 and the future plan of EAST-NBIs.

Estimation of Ion Beam Trajectories for a Slot Aperture Accelerator of Long-Pulse Ion Source in Neutral Beam Injector

A neutral beam injection (NBI) system has been developed and is being tested for an Experimental Advanced Superconducting Tokamak (EAST) device. The NBI system needs to be employed for an auxiliary heating and current drive of EAST plasmas. The first long pulse ion source (LPIS-1) has been installed in the neutral beam test bed (NBTB) system, and the performance is being tested in the NBTB. The LPIS-1 consists of a magnetic bucket plasma generator with multipole cusp-fields and a set of tetrode accelerators with slit-type apertures (a transparency of 60%). The ion beam trajectories of the accelerator column are estimated for the LPIS-1, including an original structure, with the change of slit aperture distance, plasma grid shape, grid gap distance, and voltage ratio between a plasma grid and a gradient grid using the IGUN code. This kind of calculation for the ion beam trajectory may be useful for the estimation of beam extraction characteristics and the direction of accelerator upgrade or modification, prior to the experiments of ion beam extraction.

EAST 低杂波加热对同向切向中性束碰撞力矩影响的研究

为研究低杂波加热对同向切向中性束注入的束功率沉积和碰撞力矩的影响,基于低杂波加热的实验参数,使用TRANSP程序进行了模拟分析。研究结果表明,当注入功率1.3MW、能量50keV的同向切向束时,随着LHW加热束沉积功率降低,快离子电荷交换损失增加20%;离子吸收的功率占总的束沉积功率的比例由45%增加到51%。碰撞力矩与束沉积功率的比值由1.327Nm·MW^(-1)增加到1.457Nm·MW^(-1);等离子体电子温度越高,电荷交换损失和碰撞力矩与束沉积功率比值也越大,而低杂波加热期间的束碰撞力矩保持稳定。

EAST托卡马克的中性束注入方案

高能中性束注入(Neutral beam injection,NBI)是核聚变装置托卡马克采用的芯部辅助加热和非感应电流驱动主要手段之一。本文介绍了国家大科学工程全超导托卡马克实验装置(Experimental advanced super- conducting tokamak,EAST)上的高能NBI加热方案及注入器的工程要求,并讨论了中性束在EAST等离子体中的传输等相关问题。

EAST NBI综合测试台离子源电源系统的测试研究

EAST NBI束线综合测试台已研制完成并具备一台兆瓦级离子源测试运行的全套电源设备,包括离子源灯丝电源、弧电源、加速器电源、抑制极电源、偏转磁体电源及缓冲器电源等。介绍了EAST兆瓦级离子源进行起弧放电调试运行的方式,叙述了各套离子源电源系统的设计结构、技术特点及运行控制方式,分析了离子源电源系统稳定可靠运行需要解决的各个难点,给出了EAST束线样机进行高功率及长脉冲束引出测试运行的实验结果。

EAST中性束注入电流驱动的数值模拟研究

长脉冲高参数稳态运行是EAST的主要科学目标,因此大功率的辅助加热手段是必需的。文章基于EAST实验等离子体放电数据,针对EAST不同的中性束物理实验的需要,在不同的背景等离子体和中性束参数下模拟研究中性束注入的加热和电流驱动效果,包括不同的中性束注入功率和束能量等,模拟预测结果对开展EAST中性束注入实验研究具有参考意义。

氘中性束注入到EAST内的中子产额分析

利用典型离子模型和解析方法估算了氘中性束注入到先进超导托卡马克装置（ExperimentalAdvancedSuperconductingTokamak，EAST）等离子体内的中子产额。分析了聚变中子与EAST等离子体内中心离子密度、中心离子温度及注入氘中性束能量、注入功率等参数的关系。计算结果表明，当EAST运行在典型放电参数下，能量为80keV、功率为4MW的氘中性柬注入时，EAST等离子体总聚变中子产额为-10^16n·s^-1，是热核聚变中子产额10^15n·s^-1的10倍。本文的计算结果可为制定中子辐射防护措施和EAST发展新的中子探测技术提供参考。

EAST中性束注入下快离子输运行为的研究

利用等离子体输运分析程序TRANSP和粒子导心轨道模拟程序ORBIT,结合聚变中子和等离子体储能诊断数据,对EAST(Experimental Advanced Superconducting Tokamak)托卡马克中性束注入加热时不同等离子体电流和纵场强度下的快离子输运行为进行了研究。实验和模拟结果表明:中性束反向束注入时的快离子初始轨道损失功率大于中性束同向束;中性束4条束线产生快离子初始轨道损失区域主要集中在装置中平面以下第一壁以及偏滤器区域;在EAST目前的运行参数范围内,提高等离子体电流和纵场强度,可以使等离子体中快离子的漂移轨道宽度和拉莫尔回旋半径缩小,更有利于快离子的约束,从而提高中性束的加热效率,增加聚变中子产额和等离子体储能。

EAST中性束注入快离子损失研究

利用经典导心轨道程序ORBIT,结合平衡程序EFIT和输运程序TRANSP,计算了EAST中性束注入后快离子的损失情况。结果表明,4MW(80keV)氘离子的损失份额为29%,2MW(50keV)氘离子的损失份额为31%,损失的快离子有很强的局域性。

中性束束流沿束线损失分析与沉积

分析了中性注入系统中束流在束线各部件上的损失,提出了束线上各部件的设计方案,并简单介绍了中性注入系统。

分布式高压直流缓冲器的分析与应用

高压直流系统短路故障需要通过缓冲器消耗故障能量和抑制短路电流,传统的集中式缓冲器不能满足高电压的核聚变托克马克装置中性束注入系统的要求,新的方法是沿着电源传输线安装分布式缓冲器,并在每个缓冲器两端上并联一定数量的电阻环。通过多个缓冲器将分布电容分成多个,每个缓冲器吸收的能量减少,改善缓冲器的结构。

EAST上磁位形和杂质对束离子约束和加热影响的数值模拟

利用程序ORBIT和TRANSP/NUBEAM模拟研究全超导托卡马克实验装置(EAST)等离子体位形和杂质的特征参数Z_(eff)(有效电荷数)对束离子约束和加热的影响。结果表明:在等离子体位形中,随着最后一个封闭通量表面与中面外容器壁之间的距离(gapout)和环向磁场强度的增加,快离子的损失(包含瞬时损失和波纹损失)也随之减少,因此中性束的加热效率随着gapout的增加而提高。此外,随着背景等离子体杂质的增加(即Zeff的增加),增加了束损失,导致最后束加热效率降低。选择合适的磁位形,同时降低背景的杂质含量可以增强快离子约束,提高束的加热效率。