ICRF加热下EAST快离子损失速度空间分布初步研究

基于闪烁体的快离子损失探针（Fast-Ion Loss Detector,FILD）能够测量损失快离子的速度空间分布,是研究核聚变装置中快离子损失控制机理的关键诊断手段。在东方超环（Experimental Advanced Superconducting Tokamak,EAST）上,通过FILDSIM程序在诊断图像与速度空间分布之间建立桥梁,将诊断探测到的信号转化为速度空间分布,获得了离子回旋共振加热（Ion Cyclotron Resonance Heating,ICRH）条件下的快离子损失速度空间分布,为进一步评估和控制离子回旋共振加热下的快离子损失奠定了基础。另外,通过损失快离子反向追踪,探究了探头本体遮挡对诊断探测范围的影响,为损失诊断系统进一步升级提供了依据。     

基于闪烁体的快离子损失探针的设计研究

基于闪烁体的快离子损失探针是用于测量托克马克装置中损失快离子的重要诊断设备。它能对损失快离子的能量和俯仰角进行同时测定,得到损失快离子通量随时间演化的信息,对研究快离子的约束输运行为有重要意义。针对HL-2A对损失快离子诊断的具体需求,对用于HL-2A的快离子损失探针的闪烁体屏尺寸、闪烁材料种类以及准直系统做了研究设计。同时对适用于ITER的闪烁材料种类进行了分析讨论。     

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。     

环向非对称ICRF波情形下的波感应粒子箍缩的证据

在联合欧洲环（ＪＥＴ）的近轴高功率环向非对称ＩＣＲＲ（离子回旋频率范围）加热的实验中，首次观察到了射频（ｒｆ）波感应捕获离子的粒子箍缩。当波的方向在相反的环向时，放电中探测到了明显的差异。特别是发现快离子驱动的阿尔芬本征模活性、锯齿行为和质子分布函数受到强烈的影响。大量的放电分析表明，所观测到的差异与理论预言的ＩＣＲＦ感应粒子箍缩是一致的。     

中国实验快堆缓发中子探测系统的瞬态模拟与分析

根据中国实验快堆缓发中子探测系统的结构特点和探测原理,构建了缓发中子探测系统的计算模型.基于该模型,开发了计算机模拟程序.针对不同工况和不同燃料元件包壳破损时刻,进行了缓发中子探测信号的模拟计算.计算结果基本反映了计算情况下缓发中子探测信号的发展趋势.同时,还对燃料温度和燃料燃耗对缓发中子探测信号的影响进行了物理分析.     

托卡马克中离子回旋频率范围内快波电流驱动的研究

在现在和未来的先进托卡马克装置中,离子回旋频率范围内的快波电流驱动都是一种不可或缺的非感应电流驱动方式。本文利用全波方程得到波电场和磁场分布,代入扩散系数并求解Fokker-Planck方程,采用自行编写的程序对快波在等离子体中的电子吸收功率和驱动电流等物理量进行数值求解。初步研究了快波频率和等离子体温度对电子吸收功率及电流驱动效率的影响,结果显示快波能传播到托卡马克等离子体的中心区域并被电子吸收;快波频率对电子吸收快波功率有显著的影响,在70～100 MHz波频率范围内电子对快波吸收效果较好,能有效驱动电流;另外在该频段内随着等离子体温度的升高,电子吸收效果变差。     

圆柱形与圆锥形放电腔室中氢等离子体组分与状态研究

采用圆柱形和圆锥形的放电腔室,使用氢气作为放电气体在不同的射频功率下进行了放电。使用质谱诊断和Langmuir探针诊断相结合的方法对两种放电腔室中的氢等离子体的离子组分、离子能量分布（IED）、等离子体电势、电子密度和有效电子温度进行了对比研究。根据等离子体的诊断结果,讨论了圆锥形与圆柱形两种放电腔室中的放电特性。结果表明：圆柱形放电腔室中含有更多的亚稳态氢原子H ^*,而圆锥形放电腔室中含有更多的H⁺离子。圆锥形放电腔室中等离子体具有更高的电子密度和离子密度及更低的等离子体电势。     

全超导托卡马克装置欧姆放电逃逸电子行为研究

电子发生逃逸在托卡马克等离子体中是较常见的现象,特别是在等离子体破裂阶段,会产生大量的逃逸电子。本工作利用硬X射线监测系统,并结合其它相关诊断系统研究世界上第1个运行的全超导托卡马克（EAST）装置在欧姆放电的不同阶段逃逸电子的行为。研究结果表明：在欧姆放电起始阶段,逃逸电子的初级产生过程占主导地位。随着放电的进行,逃逸电子的次级雪崩过程逐渐增长,在放电后期一直到等离子体破裂阶段,雪崩过程将占据主导地位。等离子体破裂后,因存在较高的环电压而产生了高能逃逸电子拖尾。     

NSRL电子储存环束流损失过程的M0nte-Carl0计算

高能电子和物质相互作用是一个级联簇射(shower)物理过程。NSRL电子储存环(HLS)束流损失监测系统利用这一原理,通过探测束流损失电子在储存环真空室外表面产生的shower电子,给出束流损失的有关信息。本文利用Monte-Carlo方法,采用EGS4软件包,对束流损失电子与真空室壁相互作用的过程进行模拟,给出了真空室外表面shower电子的分布特点(1)shower电子在真空室外表面是前冲性很强的粒子;(2)在垂直方向的分布是比较窄的对称分布,对束流损失探测器的安装有一定的要求;(3)打在真空室内侧壁上的电子及其产生的shower电子有机会反射到外侧壁,并进一步发生shower过程,但其影响会低两个量级以上;(4)shower电子在真空室外表面上的分布,外侧峰位要比内侧峰位位置在束流方向上后移。     

JET上在有高快离子能含量下只有ICRF放电的一种新型MHD活性

在有离子回旋共振频率（ICRF）加热和改变等离子体密度的情况下，在JET托卡马克中进行的放电中，已研究了在甚高快离子能含量时锯齿稳定问题，等离子体密度的改变是通过吹氘气加以控制的，在这些实验中，已观测到锯齿性能的惊人差别，当等离子体密度nc减小到低于某个阈值时，居齿频率和崩塌持续时间增加5倍，因为由于快离子慢化时间与nc成反比而快离子能含量随nc减小而增加，所以nc阈值相应于快离子能含量阈值，在这些实验中，当快离子能量对总等离子体抗磁能含量的贡献变得大于45％时达到此阈值，在频率介于55和65kHz之间，环向模数n=1时，有短的无锯齿周期的锯齿活性伴随有MHD活性，这种活性解释为与ICRF驱动的快离子共振的高能粒子鱼骨模，看来实验结果是与锯齿和鱼骨模的稳定性图一致的[White 1989:Theory of Tokamak Plasmas(Amsterdam:North-Holland)]，探索在此图中有甚大快离子群体的那部分。     

Simulations of first-orbit losses of neutral beam injection(NBI) fast ions on EAST

Simulations of first-orbit losses of neutral beam injection(NBI) fast ions in the EAST tokamak have been studied in detail by using the orbit-following code GYCAVA and the NBI code TGCO. Beam ion losses with the wall boundary are smaller than those with the last closed flux surface boundary. In contrast to heat loads on the wall without radio frequency wave(RFW)antennas, heat loads on the wall with RFW antennas are distributed more locally near the RFW antennas. The direction of the toroidal magnetic field dramatically affects the final positions of lost fast ions, which is related to the magnetic drift. The numerical results on heat loads of beam ions corresponding to different toroidal magnetic fields are qualitatively consistent with the experimental results. Beam ion losses increase with the beam energy for the co-current NBIs and the counter-perpendicular NBI. We have studied the behavior of fast ions produced by a small section neutral beam(beamlet) by using the numerical tool NBIT. The distributions of the loss fraction of beamlet fast ions peaked near the edge of the beam section for the counter-current NBIs, and they are related to the injection angle. This indicates that the first-orbit losses can be reduced by changing the shape of beam cross section.     

Numerical study on the loss of fast ions produced by minority ion cyclotron resonance heating in EAST

The classical prompt loss of fast ions produced by minority ion cyclotron resonance heating(ICRH)is studied by a guiding center orbit following code in the Experimental Advanced Superconducting Tokamak(EAST).It is found that the loss of fast ions produced by ICRH mainly appears in both ends of the resonance layer,while the loss of fast ions in the middle resonance layer is very small.The dominant fast loss comes from trapped ions,rather than from passing ions.Controlling the location of resonance layer at the plasma core may be more beneficial to the EAST tokamak ICRH.In addition,the loss distribution of fast ions is studied.The results show that the fast ions are mainly lost near the midplane in the poloidal direction,but almost uniformly in the toroidal direction.Moreover,we investigate the dependence of fast ion loss on the ICRH power.The simulation results show that the loss fraction of fast ions in both ends of the resonance region increases with the ion cyclotron range of frequencies(ICRF)power,but barely affects the loss of fast ions in the middle region.     

Simulations of NBI fast ion loss in the presence of toroidal field ripple on EAST

NBI fast ion losses in the presence of the toroidal field ripple on EAST have been investigated by using the orbit code GYCAVA and the NBI code TGCO. The ripple effect was included in the upgraded version of the GYCAVA code. It is found that loss regions of NBI fast ions are mainly on the low field side near the edge in the presence of ripple. For co-current NBIs, the synergy effect of ripple and Coulomb collision on fast ion losses is dominant, and fast trapped ions located on the low field side are easily lost. The ripple well loss and the ripple stochastic loss of fast ions have been identified from the heat loads of co-current NBI fast ions. The ripple stochastic loss and the collisioninduced loss are much larger than the ripple well loss. Heat loads of lost fast ions are mainly localized on the right side of the radio frequency wave antennas from the inside view toward the first wall. For counter-current NBIs, the first orbit loss due to the magnetic drift is the dominant loss channel. In addition, fast ion loss fraction with ripple and collision for each NBI linearly increases with the effective charge number, which is related to the pitch angle scattering effect.     

Numerical Study on Ripple Loss of Neutral-Beam-Injected Fast Ions in EAST

A systematic comparative study on the behaviors and loss processes of energetic beam ions in the rippled toroidal field on Experimental Advanced Superconducting Tokamak (EAST) is carried out by numerical simulations. The predicted loss fractions of either co-injected or counter-injected neutral beam ions for typical EAST experiments are 9–16 %; while for low current experiments, the ripple loss domain is enlarged with the increase of the safety factor q, resulting in enhanced beam ions loss. In addition, Counter-injected ions give rise to more lost fractions in the relatively high-energy range, and fewer of them distribute into the core plasma region, which suggest that the co-injection scheme is somewhat preferable for plasma heating. Moreover, the total losses of energetic beam ions in both co-injection and counter-injection geometries are seen to be due entirely to the delayed losses owing to a synergistic effect of collisions and ripple. Finally, potential first wall damage appears to be avoidable for long pulse neutral beam injection scenarios.     

Effects of fast ions produced by ICRF heating on the pressure at EAST

Ion cyclotron resonance heating(ICRH),which can produce fast ions,is an important auxiliary heating method at EAST.To analyze the effect of ICRH-induced fast ions on the plasma pressure at EAST,simulations are performed using TRANSP and TORIC codes.It is found that the ICRF-induced fast ion pressure cannot be negligible when the ICRF power is sufficiently high.The magnitude of the total ion pressure can be raised up to 60%of the total pressure as the input power rises above 3 MW.The pressure profile is also significantly modified when the resonant layer is changed.It is shown that by changing the wave frequency and antenna position,the total ion pressure profile can be broadened,which might provide an option for profile control at EAST.     

Evaluation of NBI absorption and fast ion stored energy to improve thermal energy confinement time calculation in EAST

The absorption of neutral beam power and the fast ion stored energy in EAST plasmas with neutral beam injection(NBI)is analyzed to improve the calculation of thermal energy confinement time.The neutral beam power absorption and fast ion stored energy are systematically calculated using the TRANSP code,through the investigation of global parameters including plasma current,line averaged density and beam energy.Results have shown that scaling laws for the NBI absorption coefficient and fast ion energy rate are obtained through statistical analysis.A comparison of the confinement improvement factor H98y2 with these new scaling laws against those assuming fixed coefficients is given.     

Effect of Plasma Rotation on Neutral Beam Heating and Current Drive in Tokamaks

For a rapidly rotating plasma, the effects of the resulting Doppler shift have to be included in the neoclassical theory of neutral beam heating, current drive, and plasma transport. In this paper, an improved simulation of neutral beam injection (NBI) and current drive in rotating plasmas is introduced. NBI is simulated using the Monte Carlo code NUBEAM along with the transport code ONETWO. The physical characteristics of heating and current drive for co- and counter-NBI are investigated for non-rotating, co-rotating, and counter-rotating plasmas, all of which can take place in the experiments. In general, it is found that rotation of the plasma can increase the NBI power deposition on the plasma electrons but has little effect on the ions. Moreover, plasma heating by co-NBI is more efficient than that by counter-NBI. For neutral beam current drive, because of the Doppler shift, co-rotation (counter-rotation) of the bulk plasma tends to decrease the co-NBI (counter-NBI) driven current. On the other hand, due to trapping and orbit loss of the fast ions, co-rotation (counter-rotation) has little effect on the counter-NBI (co-NBI) driven current. The results are applied to the forthcoming NBI heating and current drive experiments of the EAST tokamak and should also be useful in the design of experiments in ITER.     

Calculation of the energy loss of fast multicharged ions in solids

The application of a classical approach to the energy loss calculation for fast multicharged ions in solids provides energy losses or kinetic energy electrons and for inner shell holes separately. The calculated total energy losses differ from the tabulated data by less than 20%.     

R&D progress of high power ion source on EAST-NBI

The neutral beam injector(NBI) system was designed and developed mainly for the plasma heating on the Experimental Advanced Superconducting Tokamak(EAST). The high power ion source is the key part of the NBI. A hot cathode ion source was used on the EAST-NBI. The ion source was conditioned on the ion source test bed with hydrogen gas and achieved the designed parameters. The deuterium gas was used when it moved to the EAST-NBI. The main performance of the ion source on EAST is presented in this paper. The highest beam power of 4.5 MW in NBI-1 and 2.75 MW in NBI-2 was achieved. The total neutral beam power is about 4.5 MW. The long pulse beam of 100 s is injected into the EAST plasma too.     

Experimental study on fast electron generation during internal crash

Hard x-ray(HXR) burst is found during internal crash in the flat top current stage of experimental advanced superconducting tokamak(EAST) discharges and it is caused by fast electrons. The generated electrons during internal crashes may be an operational safety issue in advanced tokamaks. During an internal crash, locations of fast electron generation from HXR evolution agree with areas of magnetic reconnection from soft x-ray(SXR) tomographic reconstruction. Further statistical analyses show a 27 μs time difference between SXR crashes and HXR bursts, and the agreement between time broadening of HXR bursts and estimated characteristic time of magnetic reconnection in EAST. The magnetic reconnections during internal crash are proved to generate fast electrons, by both spatial and temporal agreements.