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On benchmarking of simulations of particle transport in ITER

机译:关于ITER中粒子传输模拟的基准测试

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摘要

We report results of benchmarking of core particle transport simulations by a collection of codes widely used in transport modelling of tokamak plasmas. Our analysis includes formulation of transport equations, difference between electron and ion solvers, comparison of modules of the pellet and edge gas fuelling on the ITER baseline scenario. During the first phase of benchmarking we address the particle transport effects in the stationary phase. Firstly, simulations are performed with identical sources, sinks, transport coefficients, and boundary conditions prescribed in the flattop H-mode phase. The transformation of ion particle transport equations is introduced so to directly compare their results to electron transport solvers. Secondly, the pellet fuelling models are benchmarked in various conditions to evaluate the dependency of the pellet deposition on the pellet volume, injection side, pedestal, and separatrix parameters. Thirdly, edge gas fuelling is benchmarked to assess sensitivities of source profile predictions to uncertainties in plasma conditions and detailed model assumptions. At the second phase, we address particle transport effects in the time- evolving plasma including the current ramp-up to the ramp-down phase. The ion and the electron solvers are benchmarked together. Differences between the simulation results of the solvers are investigated in terms of equilibrium, grid resolution, radial coordinate, radial grid distribution, and plasma volume evolution term. We found that the selection of the radial coordinate can yield prominent differences between the solvers mainly due to differences in the edge grid distribution. The simulations reveal that electron and ion solvers predict noticeably different density peaking for the same diffusion and pinch velocity while with the peaked profile of helium, expected in fusion reactors. The fuelling benchmarking shows that gas puffing is not efficient for core fuelling in H-modes and density control should be done by the high field side pellet injection in contrast to present machines.
机译:我们通过在托卡马克等离子体的传输模型中广泛使用的代码集合报告核心粒子传输模拟的基准测试结果。我们的分析包括运输方程的公式化,电子和离子求解器之间的差异,在ITER基准情景下对颗粒和边气加气模块的比较。在基准测试的第一阶段,我们讨论了固定阶段的粒子传输效应。首先,在平顶H模式阶段中使用相同的源,接收器,传输系数和边界条件进行仿真。引入了离子粒子传输方程的变换,以便将其结果直接与电子传输求解器进行比较。其次,在各种条件下对颗粒燃料模型进行基准测试,以评估颗粒沉积对颗粒体积,进样侧,基座和分离参数的依赖性。第三,对边缘气体燃料进行基准测试,以评估源剖面预测对等离子条件和详细模型假设不确定性的敏感性。在第二阶段,我们讨论了随时间变化的等离子体中的粒子传输效应,包括电流逐渐上升到下降阶段。离子和电子求解器一起进行了基准测试。研究了求解器的模拟结果之间的差异,包括平衡,网格分辨率,径向坐标,径向网格分布和等离子体体积演化项。我们发现,由于边缘网格分布的差异,径向坐标的选择会在求解器之间产生明显的差异。模拟结果表明,对于相同的扩散和收缩速度,电子和离子解算器预测的密度峰值将显着不同,而聚变反应堆中预期的氦的峰值曲线将有所不同。加油基准测试表明,与现有机器相比,在H模式下,气体吹气对堆芯加油效率不高,并且应该通过高场侧颗粒注入来进行密度控制。

著录项

  • 来源
    《Nuclear fusion》 |2019年第7期|076026.1-076026.24|共24页
  • 作者单位

    Seoul Natl Univ, Dept Nucl Engn, Seoul, South Korea;

    United Kingdom Atom Energy Author, Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England;

    ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France;

    Seoul Natl Univ, Dept Nucl Engn, Seoul, South Korea;

    Seoul Natl Univ, Dept Nucl Engn, Seoul, South Korea;

    Seoul Natl Univ, Dept Nucl Engn, Seoul, South Korea;

    Eindhoven Univ Technol, Eindhoven, Netherlands;

    Kyoto Univ, Kyoto, Japan;

    CEA, IRFM, F-13108 St Paul Les Durance, France;

    Natl Inst Quantum & Radiol Sci & Technol, Naka, Ibaraki 3110193, Japan;

    Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA;

    ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France;

    Oak Ridge Natl Lab, Oak Ridge, TN USA;

    Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA;

    Ecole Polytech Fed Lausanne, SPC, CH-1015 Lausanne, Switzerland;

    JET Exploitat Unit, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England;

    Chalmers Univ Technol, Dept Space Earth & Environm, Gothenburg, Sweden;

    Ecole Polytech Fed Lausanne, SPC, CH-1015 Lausanne, Switzerland;

    EUROfusion, Garching, Germany;

    King Mongkuts Univ Technol Thonburi, Bangkok, Thailand;

    Princeton Plasma Phys Lab, POB 451, Princeton, NJ 08543 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    particle transport; pellet fuelling; gas fuelling; tokamak; modelling; benchmarking;

    机译:颗粒运输;颗粒燃料;气体燃料;托卡马克;建模;基准测试;
  • 入库时间 2022-08-18 04:20:07

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