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Simulation of transport in the ignited ITER with 1.5-D predictive code

机译:用1.5D预测代码模拟被点燃的ITER中的运输

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摘要

The confinement in the bulk and scrape-off layer plasmas of the ITER EDA and CDA is investigated with special versions of the 1.5-D BALDUR predictive transport code for the case of peaked density profiles (Cu=1.0). The code self-consistently computes 2-D equilibria and solves 1-D transport equations with empirical transport coefficients for the ohmic, L and ELMy H mode regimes. Self-sustained steady state thermonuclear burn is demonstrated for up to 500 s. It is shown to be compatible with the strong radiation losses for divertor heat load reduction caused by the seeded impurities iron, neon and argon. The corresponding global and local energy and particle transport are presented. The required radiation corrected energy confinement times of the EDA and CDA are found to be close to 4 s, which is attainable according to the ITER ELMy H mode scalings. In the reference cases, the steady state helium fraction is 7%, which already causes significant dilution of the DT fuel. The fractions of iron, neon and argon needed for the prescribed radiative power loss are given. It is shown that high radiative losses from the confinement zone, mainly by bremsstrahlung, cannot be avoided. The radiation profiles of iron and argon are found to be the same, with two thirds of the total radiation being emitted from closed flux surfaces. Fuel dilution due to iron and argon is small. The neon radiation is more peripheral, since only half of the total radiative power is lost within the separatrix. But neon is found to cause high fuel. Dilution. The combined dilution effect by helium and neon conflicts with burn control, self-sustained burn and divertor power reduction. Raising the helium fraction above 10% leads to the same difficulties owing to fuel dilution. The high helium levels of the present EDA design are thus unacceptable. For the reference EDA case, the self-consistent electron density and temperature at the separatrix are 5.6*1019 m-3 and 130 eV, respectively.
机译:对于峰值密度分布(Cu = 1.0)的情况,使用1.5D BALDUR预测输运代码的特殊版本研究了ITER EDA和CDA的体层和刮除层血浆的局限性。该代码自洽地计算2维平衡,并针对欧姆,L和ELMy H模式体系以经验传输系数求解一维传输方程。自我维持的稳态热核燃烧时间长达500 s。它显示出与种子杂质铁,氖和氩引起的减少辐射器热负荷的强辐射损失兼容。介绍了相应的全局和局部能量与粒子传输。发现所需的EDA和CDA的辐射校正能量限制时间接近4 s,这可以根据ITER ELMy H模式缩放达到。在参考案例中,稳态氦气含量为7%,这已经导致DT燃料的大量稀释。给出了规定的辐射功率损耗所需的铁,氖和氩的分数。结果表明,不能避免主要由致辐射引起的来自限制区的高辐射损失。铁和氩的辐射分布图是相同的,总辐射的三分之二是从封闭的通量表面发射的。铁和氩引起的燃料稀释很小。霓虹辐射的边缘更强,因为在头皮内仅损失了总辐射功率的一半。但是发现氖会引起高油耗。稀释。氦和氖的混合稀释作用与燃烧控制,自持燃烧和分压器功率降低相冲突。由于燃料稀释,将氦气分数提高到10%以上会导致同样的困难。因此,当前EDA设计中的高氦水平是不可接受的。对于参考EDA情况,分离层的自洽电子密度和温度分别为5.6 * 1019 m-3和130 eV。

著录项

  • 来源
    《Nuclear fusion》 |1995年第1期|p. 39-58|共20页
  • 作者

    G. Becker;

  • 作者单位

    Max-Planck-Inst. fur Plasmaphys., Garching bei Munchen, Germany;

  • 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 原子核物理学、高能物理学;
  • 关键词

  • 入库时间 2022-08-18 01:10:36

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