内爆圆柱套筒磁通量压缩的磁流体力学计算

在一维反应流体动力学程序SSS的基础上扩充编制一维磁流体力学计算编码SSS/MHD,并对炸药内爆驱动的圆柱形套筒磁通量聚积发生器(MC-1装置)进行了一维磁流体力学模拟计算。分析了空腔磁场向压缩套筒和样品套筒壁中的磁扩散现象,结果表明,在压缩套筒壁中距离空腔0.2mm处的磁感应强度最大值只有十几T;而在样品套筒壁中距离空腔0.2mm处的磁感应强度最大值达到几百T,这主要是内外套筒运动速度不同,电磁力与内爆作用力平衡引起的。计算了空腔中磁感应强度的变化曲线和样品套筒内壁的速度历程曲线,得到与实验测试符合的结果。     

磁驱动准等熵压缩铝物理量的数值分析

根据一维磁流体力学计算程序SSS/MHD的控制方程组,建立了磁驱动准等熵压缩台阶铝的计算模型,并对铝中的物理量变化过程进行了数值计算。在计算得到的电流和样品后界面粒子速度历程与实验测试结果相符合的基础上,分析了负载构型(样品)的动态电感变化、磁扩散规律,以及温度、密度、压力和速度等物理量的分布和变化规律。研究结果对深入认识磁驱动准等熵压缩物理过程和改进实验设计具有重要意义。     

爆轰驱动固体套筒压缩磁场计算及准等熵过程分析

采用构形磁流体力学计算程序SSS/MHD对炸药爆轰驱动固体套筒压缩磁场实验进行了一维磁流体力学模拟计算, 得到空腔磁场以及样品管内壁速度随时间的变化历程, 分别与磁探针和激光干涉测量的实验结果符合. 由分幅照相结果阐述了套筒压缩空腔磁场过程中的屈曲失稳和Bell-Plesset不稳定性现象. 分析了样品管和套筒中的磁扩散、涡流和磁压力的变化规律. 结果表明, 由于聚心运动下样品管和套筒的运动速度不同、电磁力和内爆作用力平衡等原因, 样品管内靠近磁腔处的磁场、涡流和磁压力均高于套筒内距磁腔相同位置处的结果. 讨论了样品管内距磁腔0.05 mm处的熵增随该点压缩度的变化, 最大熵增与样品管材料定容比热的比值在10%左右, 爆炸磁压缩实验过程的等熵程度较高.     

电磁内爆的一维显式数值模拟

 提出了一个用于电磁内爆过程数值模拟的一维磁流体力学显式模型，对中物院流体物理研究所1 MJ电容器组电磁内爆优化方案进行了计算，并将计算结果与一维德式模型的结果进行了比较。     

三维柱腔内辐射输运的一维模拟

在惯性约束聚变实验中,使用一维辐射流体力学程序模拟辐射在管壁约束的介质中的传输,因为无法考虑管壁辐射漏失等二维或三维边缘效应而引入了较大的误差.通过解析的视角因子公式和反照率定标公式来模拟X射线在管壁中的损失以及腔壁开口的漏失等边缘效应,对一维辐射流体力学程序MULTI的辐射输运计算进行了修改,成功模拟了X射线辐照下金等离子体的界面运动轨迹,比不考虑边缘漏失更接近实验测量结果,证明了该方法的有效性.     

一维磁化套筒惯性聚变模拟程序的设计与校验

在调研跟踪国外磁化套筒惯性聚变(MagLIF)研究领域最新进展的基础上,以一维磁流体力学方程为基础,结合氘氚燃料能量交换方程,建立一维磁化套筒惯性聚变物理模型,并使用Fortran语言编写完成一维数值模拟程序MagLIF-1D;通过与圣地亚实验室LASNEX,HYDRA等程序计算结果对比展示,完成程序校验工作,讨论后认为程序计算结果存在差异的主要原因可能来自不同程序对于材料状态方程库的选择;通过计算,MagLIF-1D程序可以直接获得内爆速度、燃料压力、燃料密度、聚变产额等关键物理量,这为后续更好地开展磁化套筒惯性聚变实验设计提供了有力工具。     

铝丝阵列Z箍缩的辐射磁流体动力学过程

 在拉格朗日坐标系下，建立了描述Z箍缩等离子体内爆动力学过程的一维三温辐射磁流体力学方程组，并编制了相应的拉氏程序。利用该程序对美国Sandia实验室Saturn装置上的铝丝阵列内爆实验进行了数值模拟，得到了内爆等离子体各参量的时空分布。其中内爆到心时刻、X光峰值功率、X光总能量等计算结果与实验结果基本一致。表明所建立的物理模型和编制的程序是合理和可靠的。     

双层钨丝阵的Z箍缩动力学过程研究

基于Z箍缩零维模型、丝阵碰撞假设和箍缩动能最大化的优化原则，对美国Sandia实验室Z装置的典型双层钨丝阵负载进行了优化分析，结果表明它基本上是优化的.在丝阵碰撞假设下，利用一维三温辐射磁流体力学程序对其箍缩过程进行了数值模拟，模拟结果再现了Z箍缩过程的一维时空演化过程，得到了内外层丝阵的运动轨迹和驱动电流在它们之间的转移规律，并将计算得到的宏观结果与实验结果进行了比较.表明丝阵相互作用的碰撞假设有合理性. 关键词： Z箍缩 双层钨丝阵 零维模型 一维辐射磁流体     

电爆炸箔驱动绝缘飞片的一维数值模拟

 在一维有限差分反应流体动力学程序SSS中引入电爆炸模型,在此基础上结合新引入的物态方程库,开展了电爆炸加载下飞片运动过程的数值模拟研究。计算结果与实验结果基本吻合,表明SSS对电爆炸驱动飞片的过程的模拟是可靠的,为电炮加载技术的优化设计和电爆炸驱动飞片物理过程的进一步研究提供了一套有效的计算方法和程序。     

螺旋型爆磁压缩脉冲发生器电阻及磁通损失的数值计算

基于电流和磁扩散方程,讨论了螺旋型爆磁压缩脉冲发生器(MFCG)中的电阻与磁通损耗问题,将相关的接触电阻模型、欧姆电阻的趋肤效应与邻近效应模型具体应用到2维爆轰磁流体力学程序MF-CG-Ⅳ中,进一步完善了程序的物理功能。并选用美国德克萨斯理工大学简单绕制的螺旋型爆磁压缩脉冲发生器的实验结果对新增模块进行了考证,计算结果符合物理规律,且与实验测量吻合较好。     

Comparison benchmark between tokamak simulation code and TokSys for Chinese Fusion Engineering Test Reactor vertical displacement control design

Vertical displacement event(VDE) is a big challenge to the existing tokamak equipment and that being designed. As a Chinese next-step tokamak, the Chinese Fusion Engineering Test Reactor(CFETR) has to pay attention to the VDE study with full-fledged numerical codes during its conceptual design. The tokamak simulation code(TSC) is a free boundary time-dependent axisymmetric tokamak simulation code developed in PPPL, which advances the MHD equations describing the evolution of the plasma in a rectangular domain. The electromagnetic interactions between the surrounding conductor circuits and the plasma are solved self-consistently. The TokSys code is a generic modeling and simulation environment developed in GA. Its RZIP model treats the plasma as a fixed spatial distribution of currents which couple with the surrounding conductors through circuit equations. Both codes have been individually used for the VDE study on many tokamak devices, such as JT-60U, EAST, NSTX, DIII-D, and ITER. Considering the model differences, benchmark work is needed to answer whether they reproduce each other's results correctly. In this paper, the TSC and TokSys codes are used for analyzing the CFETR vertical instability passive and active controls design simultaneously. It is shown that with the same inputs, the results from these two codes conform with each other.     

Fast ion induced shearing of 2D Alfvén eigenmodes measured by electron cyclotron emission imaging

Two-dimensional images of electron temperature perturbations are obtained with electron cyclotron emission imaging (ECEI) on the DIII-D tokamak and compared to Alfvén eigenmode structures obtained by numerical modeling using both ideal MHD and hybrid MHD-gyrofluid codes. While many features of the observations are found to be in excellent agreement with simulations using an ideal MHD code (NOVA), other characteristics distinctly reveal the influence of fast ions on the mode structures. These features are found to be well described by the nonperturbative hybrid MHD-gyrofluid model TAEFL.     

二维磁驱动数值模拟程序MDSC2的验证与确认

为了对磁驱动实验提供高置信度的数值模拟,需要开展磁流体力学程序的验证与确认。采用人为解比较法、网格收敛性研究和与成熟程序比较等方法,对二维磁驱动数值模拟程序MDSC2进行了程序验证。数值模拟表明:MDSC2程序正确地表示了磁流体力学模型,其中热扩散、磁扩散的离散格式具有二阶收敛精度。采用与磁驱动实验相比较的方法,进行了MDSC2程序的确认。对聚龙一号装置上的PTS-061发次磁驱动单侧飞片发射和PTS-122发次磁驱动双侧飞片发射实验进行了模拟,模拟的飞片自由面速度与实验测量的飞片自由面速度相一致;对FP-1装置上的固体套筒实验进行了模拟,模拟的套筒内外半径与实验测量结果相一致。MDSC2程序能正确模拟磁驱动单侧飞片发射、磁驱动双侧飞片发射和磁驱动固体套筒等磁驱动实验。     

FOI-PERFECT程序对电磁驱动高能量密度系统的三维弛豫磁流体力学模拟

提出一个完整的弛豫磁流体力学模型用于电磁驱动高能量密度系统的数值模拟, 它由弛豫电磁波动、弛豫热输运、P1/3近似辐射输运以及流体力学构成。电磁部分在真空区退化为电磁传播, 在等离子体物质区退化为磁扩散近似, 并且相速和群速是有上界的。这意味着弛豫磁流体力学能退化到传统的电阻性磁流体力学, 并且能用显式方法数值求解, 便于大规模高效并行化。基于此弛豫磁流体力学模型开发了三维辐射磁流体力学程序FOI-PERFECT, 指出了所采用的关键数值技术, 并给出了一些应用例子。     

聚变堆液态包层准二维磁流体湍流模型研究

为研究聚变堆氚增殖包层中液态金属湍流磁流体动力学(MHD)效应,开发了一种新的准二维单方程 MHD 湍流模型,并进行了相关数值模拟程序的编制及验证。对于矩形管道中的准二维 MHD 湍流流动,三维流 动主要发生在哈德曼层中,中心的主流区呈现出二维流动。为了反映这种特殊的流动特征,新湍流模型在标准 k-ε 模型的基础之上去掉了传统的耗散项,代之以电磁耗散项来模拟湍流 MHD 效应。同时,采用 Bradshaw 假设来对 湍流涡粘系数进行模化。为验证该湍流模型是否合理,编制了相关数值模拟程序,并利用直接数值模拟(DNS)结 果对该程序进行了校正,数值模拟结果与 DNS 结果吻合较好。计算结果表明,该湍流模型可应用于聚变堆液态 包层 MHD 湍流流动的数值模拟。     

Numerical Simulation of the 12 May 1997 CME Event

Our newly developed CESE MHD model is used to simulate sun-earth connection event with the well-studied 12 May 1997 CME event as an example. The main features and approximations of our numerical model are as follows： （1） The modifed conservation element and solution element （CESE） numerical scheme in spherical geometry is implemented in our code. （2） The background solar wind is derived from a 3D time-dependent numerical MHD model by input measured photospheric magnetic fields. （3） Transient disturbances are derived from solar surface by introducing a mass flow of hot plasma. The numerical simulation has enabled us to predict the arrival of the interplanetary shock and provided us with a relatively satisfactory comparison with the WIND spacecraft observations.     

Classical and semirelativistic magnetohydrodynamics with anisotropic ion pressure

We study the magnetohydrodynamics (MHD) equations with anisotropic ion pressure and isotropic electron pressure under both the classical and semirelativistic approximations in order to develop a numerical model. The dispersion relation as well as the characteristic wave speeds are derived. In addition to the exact wave speed solutions, we also provide efficient approximate formulas for the semirelativistic magnetosonic speeds. The equations are discretized with the Rusanov and Harten-Lax-van Leer numerical schemes and implemented into the BATS-R-US MHD code. We perform a set of verification tests.     

XTOR-2F: A fully implicit Newton–Krylov solver applied to nonlinear 3D extended MHD in tokamaks

XTOR-2F solves a set of extended magnetohydrodynamic (MHD) equations in toroidal tokamak geometry. In the original XTOR code, the time stepping is handled by a semi-implicit method 1, 2 and 3. Moderate changes were necessary to transform it into a fully implicit one using the NITSOL library with Newton–Krylov methods of solution for nonlinear system of equations [4]. After addressing the sensitive issue of preconditioning and time step tuning, the performances of the semi-implicit and the implicit methods are compared for the nonlinear simulation of an internal kink mode test case within the framework of resistive MHD including anisotropic thermal transport. A convergence study comparing the semi-implicit and the implicit schemes is presented. Our main conclusion is that on one hand the Newton–Krylov implicit method, when applied to basic one fluid MHD is more computationally costly than the semi-implicit one by a factor 3 for a given numerical accuracy. But on the other hand, the implicit method allows to address challenging issues beyond MHD. By testing the Newton–Krylov method with diamagnetic modifications on the dynamics of the internal kink, some numerical issues, to be addressed further, are emphasized.