Geant4 simulation of fast-electron bremsstrahlung imaging at the HL-3 tokamak

To further research on high-parameter plasma,we plan to develop a two-dimensional hard X-ray(HXR)imaging system at the HL-3 tokamak to measure HXRs with energies ranging from 20 to 300 keV.The application of an array-structured detector ensures that this system can measure HXR-radiation spectra from the entire plasma cross section.Therefore,it is suitable for the study of fast-electron physics,such as radio-frequency wave current drives,fast electrons driving instabilities,and plasma disruptions in fusion research.In this study,we develop a simulation for calculating fast-electron bremsstrahlung in the HL-3 tokamak based on the Monte Carlo simulation code Geant4,in which the plasma geometry and forward scattering of fast-electron bremsstrahlung are considered.The preliminary calculation results indicate that the HXR energy deposi-tion on the detector is symmetrically distributed,even though the plasma distribution is asymmetric owing to the toroidal effect.These simulation results are helpful in constructing the relationship between the energy deposition on the detector and parameter distribution on the plasma cross section during HL-3 experiments.This is beneficial for the reconstruction of the fast-electron-distribution function and for optimizing the design of the HXR-imaging system.

Kinetic equilibrium reconstruction with internal safety factor profile constraints on EAST tokamak

Reconstruction of plasma equilibrium plays an important role in the analysis and simulation of plasma experiments. The kinetic equilibrium reconstruction with pressure and edge current constraints has been employed on EAST tokamak. However, the internal safety factor(q) profile is not accurate. This paper proposes a new way of incorporating q profile constraints into kinetic equilibrium reconstruction. The q profile is yielded from the Polarimeter Interferometer(POINT)reconstruction. Virtual probes containing information on q profile constraints are added to inputs of the kinetic equilibrium reconstruction program to obtain the final equilibrium. The new equilibrium produces a more accurate internal q profile. This improved method would help analyze EAST experiments.

Deep learning approaches to recover the plasma current density profile from the safety factor based on Grad–Shafranov solutions across multiple tokamaks

Many magnetohydrodynamic stability analyses require generation of a set of equilibria with a fixed safety factor q-profile while varying other plasma parameters.A neural network(NN)-based approach is investigated that facilitates such a process.Both multilayer perceptron(MLP)-based NN and convolutional neural network(CNN)models are trained to map the q-profile to the plasma current density J-profile,and vice versa,while satisfying the Grad–Shafranov radial force balance constraint.When the initial target models are trained,using a database of semianalytically constructed numerical equilibria,an initial CNN with one convolutional layer is found to perform better than an initial MLP model.In particular,a trained initial CNN model can also predict the q-or J-profile for experimental tokamak equilibria.The performance of both initial target models is further improved by fine-tuning the training database,i.e.by adding realistic experimental equilibria with Gaussian noise.The fine-tuned target models,referred to as fine-tuned MLP and fine-tuned CNN,well reproduce the target q-or J-profile across multiple tokamak devices.As an important application,these NN-based equilibrium profile convertors can be utilized to provide a good initial guess for iterative equilibrium solvers,where the desired input quantity is the safety factor instead of the plasma current density.

Ion heat transport in electron cyclotron resonance heated L-mode plasma on the T-10 tokamak

Anomalous ion heat transport is analyzed in the T-10 tokamak plasma heated with electron cyclotron resonance heating(ECRH) in second-harmonic extra-ordinary mode. Predictive modeling with empirical scaling for Ohmical heat conductivity shows that in ECRH plasmas the calculated ion temperature could be overestimated, so an increase of anomalous ion heat transport is required. To study this effect two scans are presented: over the EC resonance position and over the ECRH power. The EC resonance position varies from the high-field side to the low-field side by variation of the toroidal magnetic field. The scan over the heating power is presented with on-axis and mixed ECRH regimes. Discharges with high anomalous ion heat transport are obtained in all considered regimes. In these discharges the power balance ion heat conductivity exceeds the neoclassical level by up to 10 times. The high ion heat transport regimes are distinguished by three parameters: the ratio Te/Ti, the normalized electron density gradient R/■, and the ion–ion collisionality νii~*. The combination of high Te/Ti, high νii~*, and R/■=6-10 results in values of normalized anomalous ion heat fluxes up to 10 times higher than in the low transport scenario.

Numerical analysis for the free-boundary current reversal equilibrium in the AC plasma current operation in a tokamak

In recent decades, tokamak discharges with zero total toroidal current have been reported in tokamak experiments, and this is one of the key problems in alternating current(AC) operations.An efficient free-boundary equilibrium code is developed to investigate such advanced tokamak discharges with current reversal equilibrium configuration. The calculation results show that the reversal current equilibrium can maintain finite pressure and also has considerable effects on the position of the X-point and the magnetic separatrix shape, and hence also on the position of the strike point on the divertor plates, which is extremely useful for magnetic design, MHD stability analysis, and experimental data analysis etc. for the AC plasma current operation on tokamaks.

A dual-route optical emission spectroscopy diagnostic with wide spectral range and high wavelength resolution on HL-2A tokamak

A dual-route optical emission spectroscopy(D-OES)diagnostic is newly developed to monitor the optical emission from the X-point plasma region on the HL-2 A tokamak.This diagnostic is composed of an imaging system,a beam-splitting system for dual-route measurements,fiber bundles,a spectrometer system,and a control and acquisition system.One route is used to obtain wide-spectral-range spectra,and the other route is used to acquire high-wavelengthresolution line shapes.The spectral resolution of the wide-range spectrometers is 0.8 nm with a coverage of 800 nm(@200-1000 nm).The spectral resolution of the high-resolution spectrometer is 0.01 nm with a coverage of 6 nm(@200-660 nm).The spatial resolution of each route of D-OES is about 4 cm with 11 channels.The temporal resolution is 16 ms at maximum in the single-channel mode.Wide-range spectra(containing Balmer series and a Fulcher band)and highly resolved Ha line shapes are obtained by D-OES in the hydrogen glow discharge in the lab.D-OES measurements are carried out in the high-density deuterium experiments of HL-2A.The electron density n_(e)and deuterium temperature T_(D) in the X-point multifaceted asymmetric radiation from the edge(MARFE)region are derived simultaneously by fitting the measured D_(a) shape.The density n_(e)is observed to increase from~8.7×10^(18)m^(-3)to~7.8×10^(19)m^(-3),and the temperature T_(D)drops from~14.4 eV to~2.3 eV after the onset of MARFE in the discharge#38260.

A synthetic diagnostics platform for microwave imaging diagnostics in tokamaks

Interpreting experimental diagnostics data in tokamaks,while considering non-ideal effects,is challenging due to the complexity of plasmas.To address this challenge,a general synthetic diagnostics(GSD)platform has been established that facilitates microwave imaging reflectometry and electron cyclotron emission imaging.This platform utilizes plasma profiles as input and incorporates the finite-difference time domain,ray tracing and the radiative transfer equation to calculate the propagation of plasma spontaneous radiation and the external electromagnetic field in plasmas.Benchmark tests for classical cases have been conducted to verify the accuracy of every core module in the GSD platform.Finally,2D imaging of a typical electron temperature distribution is reproduced by this platform and the results are consistent with the given real experimental data.This platform also has the potential to be extended to 3D electromagnetic field simulations and other microwave diagnostics such as cross-polarization scattering.

Simulation of ion cyclotron wave heating in the EXL-50U spherical tokamak based on dispersion relations

This study investigates the single-pass absorption(SPA) of ion cyclotron range of frequency(ICRF) heating in hydrogen plasma of the EXL-50U spherical tokamak,which is an upgraded EXL-50 device with a central solenoid and a stronger magnetic field.The reliability of the kinetic dispersion equation is confirmed by the one-dimensional full-wave code,and the applicability of Porkolab's simplified theoretical SPA model is discussed based on the kinetic dispersion equation.Simulations are conducted to investigate the heating effects of the fundamental and second harmonic frequencies.The results indicate that with the design parameters of the EXL-50U device,the SPA for second harmonic heating is 63%,while the SPA for fundamental heating is 13%.Additionally,the optimal injection frequencies are 23 MHz at 0.9 T and 31 MHz at 1.2 T.The wave vector of the antenna parallel to the magnetic field,with a value of k_‖=7.5 m^(-1),falls within the optimal heating region.Simulations reveal that the ICRF heating system can play an important role in the ion heating of the EXL-50U.

First results of CO_(2) dispersion interferometer on EAST tokamak

A dispersion interferometer(DI)has been installed and operates on the Experimental Advanced Superconducting Tokamak(EAST).This DI system utilizes a continuous-wave 9.3μm CO_(2)laser source to measure line-averaged electron densities accurately.In contrast to conventional interferometers,the DI does not require substantial vibration isolations or compensating systems to reduce the impact of vibrations in the optical path.It also employs a ratio of modulation amplitudes,ensuring it remains immune to the variations in detected intensities.Without a variation compensation system,the DI system on EAST reaches a density resolution of less than1.8×10^(-2)πrad and a temporal resolution of 20μs.The measurements made by the POlarimeterINTerferometer(POINT)system and the far-infrared hydrogen cyanide(HCN)interferometer are remarkably consistent with the DI’s results.The possibility of fringe jumps and the impact of refraction in high-density discharge can be significantly decreased using a shorter wavelength laser source.A rapid density change of 3×10^(19)m^(-3)during 0.15 s has been measured accurately in shot No.114755 of EAST.Additionally,the DI system demonstrates dependability and stability under 305 s long-pulse discharges in shot No.122054.

Tokamak第一壁上W/Cu材料的连接和界面应力的研究

重点讨论了适合于磁约束核聚变实验装置(Tokamak)第一壁上W/Cu复合材料连接的几种方法:电子束焊、钎焊、热等静压连接、烧结熔渗法、等离子体喷涂法,并列举了第一壁材料与热沉材料成功连接时电子束辐照热负荷实验的情况。探讨了在此连接方式下复合材料热负荷实验时应力求解方法和应力分布情况。

非圆Tokamak载流线圈的磁弹性分析

基于曲梁理论和Ｂｉｏｔ－Ｓａｖａｒｔ定律描述超导载流线圈全部形变的理论模型，采用边值问题的齐次微分方程封闭形式解析通解和非齐次微分方程数值特解相叠加的半解析半数值方法，对非圆Ｄ型Ｔｏｋａｍａｋ载流线圈弯曲，失稳的磁弹性相互作用进行了研究；并且就线圈初始扰动位移对失稳临界电流的影响也进行了定量分析．数值模拟结果表明：线圈失稳的临界电流随线圈曲率半径的增大而增大，随线圈非完全对称排列这一初始缺陷的增大而减小．

Tokamak等离子体图像诊断系统的研制

针对Tokamak等离子体放电实验中需要对等离子体进行直观诊断的需求,根据实验的特点,研制了等离子体图像诊断系统,该系统以Matrox公司的Meteor Ⅱ/Digital采集卡和UNIQ VISION公司的UC610相机等为硬件核心,采用了Visual C++多线程技术进行实时图像采集,采用了Bayer变换和Gamma校正等数字图像处理技术将采集到的Bayer格式的灰度数字图像转换为彩色数字图像;该图像诊断系统实现了Tokamak放电实验中等离子体图像实时采集、处理和诊断等功能,充分满足了等离子体放电实验诊断的要求。

大型Tokamak装置中环向场超导线圈的传热研究

分析了HT-7U超导Tokamak核聚变装置中环向场超导线圈上的涡流损耗热产生的机理和迫流式超临界氦对流换热等过程。特别针对等离子体快速破裂时,极短时间内在环向场磁体中所产生的较大的涡流损耗而引起的焦耳热,对环向场线圈盒与超导磁体之间的热传递过程加以研究。本文采用国际上通用的有限元分析软件ANSYS5.7进行计算,计算所得的结果较为乐观。

基于GA的Tokamak聚变堆芯参数优化方法研究

托卡马克(Tokamak)聚变堆芯参数优化设计是聚变及聚变驱动次临界堆设计的重要步骤之一。本文发展了基于遗传算法(GA)的堆芯参数优化方法并与中国科学院核能安全技术研究所·FDS团队研发的系统程序SYSCODE堆芯物理模块相耦合,对堆芯参数进行优化。通过优化指定的聚变堆芯设计参数(如几何尺寸、等离子体电流、环向磁场等),并满足给定的约束条件,使得单个或多个目标达到全局"最优",对于堆芯设计具有一定参考价值。

大型超导Tokamak装置纵场线圈强度的有限元分析

本文介绍了大型结构有限元分析程序COS-MOS/M在大型超导Tokamak装置机械结构设计中的应用.通过HT—7U大型超导Tokamak装置纵场线圈机械强度的有限元分析,对初始设计方案中的不合理结构进行了改进.

PTC: Full and Drift Particle Orbit Tracing Code for α Particles in Tokamak Plasmas

Fusion born α particle confinement is one of the most important issues in burning plasmas,such as ITER and CFETR.However,it is extremely complex due to the nonequilibrium characteristics,and multiple temporal and spatial scales coupling with background plasma.A numerical code using particle orbit tracing method(PTC)has been developed to study energetic particle confinement in tokamak plasmas.Both full orbit and drift orbit solvers are implemented to analyze the Larmor radius effects on α particle confinement.The elastic collisions between alpha particles and thermal plasma are calculated by a Monte Carlo method.A triangle mesh in poloidal section is generated for electromagnetic fields expression.Benchmark between PTC and ORBIT has been accomplished for verification.For CFETR burning plasmas,PTC code is used for α particle source and slowing down process calculation in 2D equilibrium.In future work,3D field like toroidal field ripples,Alfven and magnetohydrodynamics instabilities perturbation inducing α particle transport will be analyzed.

EAST Tokamak远红外激光偏振干涉仪中频稳定控制方法

利用远红外激光干涉仪对Tokamak内部电子数密度和磁场分布进行测量是控制其放电状态的重要依据。从该方法的测量原理出发,分析了中频信号频率不稳定性对电子数密度和磁场分布测量以及Tokamak放电状态实时控制的影响;针对如何提高中频频率的稳定性提出了一套以单片机为核心的控制方案和控制系统,并研制了稳频控制器;通过现场调试,对比分析了控制前后中频信号的频率变化。实验结果表明,未接入稳频控制器时,30 min内中频频率中心值变化了90 k Hz;而接入稳频控制器后,中频频率中心值始终在设定值的±5 k Hz范围内变化。这表明该控制方法和控制系统能够实现中频频率的稳定控制。

MDSplus在HT-7Tokamak聚变实验数据系统中的应用

HT-7是国家大科学工程的一个超导托卡马克装置,用于研究受控聚变反应。MDSplus作为实验数据系统的一部分,已成功地应用于HT-72004年春季聚变实验。该文叙述了Linux操作系统平台下的MDSplus在HT-7数据系统中的应用方案,论述了其技术实现细节,解决了MDSplus在多线程模式下不能安全进行数据操作的关键问题。实验表明,基于MDSplus的数据系统性能稳定,数据格式统一,为各国聚变专家进行数据分析、数据处理、系统诊断、结果共享、虚拟合作等奠定了良好的基础。

Tokamak小型化的猜想

超环体磁场对Z轴对称,设想在Z轴置一个均匀长永磁体来产生向四周辐射磁场,其幅度和离Z轴距离成反比。这个磁场产生场强的梯度变化,牵引离子向容器冲击造成不稳。仿星器是在四周构造仿照Z轴永磁体的反射磁场,用它来弥补传输磁场单调下降的部分,但不能完全弥补。Tokamak磁场问题是三维波动方程柯西方程的一个范例。如把柯西问题用傅里叶变换变化为常微分方程问题,其解的一部分传输过程的时间空间变化为柯西问题的动态解,即反映Tokamak磁场问题,另一部分解反映场理论的初始分布。再利用椭圆型方程的基本解以及δ函数的概念直接求得柯西问题的解。最后,引用非齐次方程柯西问题结合Tokamak磁场问题,设计一个外加的振动函数,以消去Tokamak的与距离成反比的磁场,使场强成为常数B0,取消仿星器达到Tokamak小型化。

COSMOS/M 有限元程序在 Tokamak 装置设计中的应用

概述了有限元技术及其在Ｔｏｋａｍａｋ装置工程设计中应用的最新发展动态。对新一代面向微型计算机的大型结构有限元分析程序ＣＯＳＭＯＳ／Ｍ作了较全面的剖析，并给出了应用该程序对核聚变实验装置中大型机械结构强度分析的应用实例。