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Simulations of KSTAR high performance steady state operation scenarios

机译:KSTAR高性能稳态操作场景的仿真

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摘要

We report the results of predictive modelling of high performance steady state operation scenarios in KSTAR. Firstly, the capabilities of steady state operation are investigated with time-dependent simulations using a free-boundary plasma equilibrium evolution code coupled with transport calculations. Secondly, the reproducibility of high performance steady state operation scenarios developed in the DIII-D tokamak, of similar size to that of KSTAR, is investigated using the experimental data taken from DIII-D. Finally, the capability of ITER-relevant steady state operation is investigated in KSTAR. It is found that KSTAR is able to establish high performance steady state operation scenarios; β_N above 3. H_(98)(y,2) up to 2.0, f_(BS) up to 0.76 and f_(NI) equals 1.0. In this work, a realistic density profile is newly introduced for predictive simulations by employing the scaling law of a density peaking factor. The influence of the current ramp-up scenario and the transport model is discussed with respect to the fusion performance and non-inductive current drive fraction in the transport simulations. As observed in the experiments, both the heating and the plasma current waveforms in the current ramp-up phase produce a strong effect on the q-profile, the fusion performance and also on the non-inductive current drive fraction in the current flattop phase. A criterion in terms of q_(min) is found to establish ITER-relevant steady state operation scenarios. This will provide a guideline for designing the current ramp-up phase in KSTAR, It is observed that the transport model also affects the predictive values of fusion performance as well as the non-inductive current drive fraction. The Weiland transport model predicts the highest fusion performance as well as non-inductive current drive fraction in KSTAR. In contrast, the GLF23 model exhibits the lowest ones. ITER-relevant advanced scenarios cannot be obtained with the GLF23 model in the conditions given in this work. Finally, ideal MHD stability is investigated for the ITER-relevant advanced scenarios in KSTAR. The methods and results presented in this paper are expected to contribute to improving the ITER and beyond ITER predictive simulations.
机译:我们报告了KSTAR中高性能稳态操作场景的预测建模结果。首先,使用自由边界等离子体平衡演化码和输运计算,通过时间相关的仿真研究了稳态操作的能力。其次,使用从DIII-D获得的实验数据,研究了DIII-D托卡马克中开发的高性能稳态操作场景的可再现性,其大小与KSTAR相似。最后,在KSTAR中研究了与ITER相关的稳态运行能力。发现KSTAR能够建立高性能的稳态操作方案; β_N高于3。H_(98)(y,2)最高为2.0,f_(BS)最高为0.76,f_(NI)等于1.0。在这项工作中,通过采用密度峰值因子的比例定律,为预测模拟新引入了逼真的密度分布。在输运仿真中,针对融合性能和无感电流驱动分数,讨论了电流加速情况和输运模型的影响。如在实验中观察到的,电流上升阶段中的加热和等离子体电流波形都对q轮廓,融合性能以及当前平顶阶段中的非感应电流驱动分数产生强烈影响。找到以q_(min)表示的标准,以建立与ITER相关的稳态操作方案。这将为设计KSTAR中的电流加速阶段提供指导。可以观察到,传输模型还会影响融合性能以及非感应电流驱动分数的预测值。 Weiland输运模型预测了KSTAR的最高融合性能以及无感电流驱动比。相反,GLF23模型展示的是最低的模型。在本文给出的条件下,无法使用GLF23模型获得与ITER相关的高级方案。最后,针对KSTAR中与ITER相关的高级方案研究了理想的MHD稳定性。预期本文中提出的方法和结果将有助于改善ITER,并超越ITER预测模拟。

著录项

  • 来源
    《Nuclear fusion》 |2009年第11期|166-175|共10页
  • 作者单位

    Department of Nuclear Engineering, Seoul National University, 599 Gwanangno, Gwanak-Gu. Seoul, 151-744, Korea National Fusion Research Institute, Gwahangno 113, Yusung-gu, Daejeon 305-333, Korea;

    Princeton Plasma Physics Laboratory, Princeton University, PO Box 451, Princeton, NJ 08543, USA;

    Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831, USA;

    National Fusion Research Institute, Gwahangno 113, Yusung-gu, Daejeon 305-333, Korea;

    Association EURATOM-CEA, CEA/DSM/DRFC, Centre de Cadarache, F-13108, Saint-Paul-lez Durance, France;

    Max-Planck-Institut fuer Plasmaphysik, EURATOM Association. D-85748 Garching, Germany;

    National Fusion Research Institute, Gwahangno 113, Yusung-gu, Daejeon 305-333, Korea;

  • 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

    plasma simulation; transport properties; tokamaks, spherical tokamaks;

    机译:等离子体模拟运输特性;托卡马克;球形托卡马克;

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