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Impact of an integrated core/SOL description on the R and B_T optimization of tokamak fusion reactors

机译：核心/ SOL集成描述对托卡马克聚变反应堆R和B_T优化的影响

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摘要

An updated and improved version of the OD divertor and scrape-off layer (SOL) model published in Siccinio et al (2016 Plasma Phys. Control. Fusion 58 125011) was coupled with the 1.5D transport code ASTRA (Pereverzev 1991 IPP Report 5/42, Pereverzev and Yushmanov 2002 IPP Report 5/98 and Fable et al 2013 Plasma Phys. Control. Fusion 55 124028). The resulting numerical tool was employed for various scans in the major radius R and in the toroidal magnetic field B_T-for different safety factors q, allowable loop voltages V_(100p) and H factors-in order to identify the most convenient choices for an electricity producing tokamak. Such a scenario analysis was carried out evaluating self-consistently, and simultaneously, the core profile and transport effects, which significantly impact on the fusion power outcome, and the divertor heat loads, which represent one of the most critical issues in view of the realization of fusion power plants (Zohm et al 2013 Nucl. Fusion 53 073019 and Wenninger et al 2017 Nucl. Fusion 57 046002). The main result is that, when divertor limits are enforced, the curves at constant electrical power output are closed on themselves in the R - B_T plane, and a maximum achievable power exists-i.e. no benefits would be obtained from a further increase in R and B_T once the optimum is reached. This result appears as an intrinsic physical limit for all those devices where a radiative SOL is needed to deal with the power exhaust, and where a lower limit on the power crossing the separatrix (e.g. because of the L-H transition) is present.
机译：在Siccinio等人（2016 Plasma Phys.Control.Fusion 58 125011）中发布的OD偏滤器和刮除层（SOL）模型的更新和改进版本与1.5D传输代码ASTRA（Pereverzev 1991 IPP报告5 / 42，Pereverzev和Yushmanov 2002 IPP报告5/98和Fable等2013 Plasma Phys.Control.Fusion 55 124028）。所得的数值工具用于在大半径R和环形磁场B_T中进行各种扫描-针对不同的安全系数q，允许的环路电压V_（100p）和H系数-以便确定最方便的电力选择生产托卡马克。进行了这样的情景分析，自洽地同时评估了对聚变功率结果有重大影响的堆芯轮廓和传输效应，以及分流器热负荷，这是从实现角度来看最关键的问题之一（Zohm等人2013 Nucl.Fusion 53 073019和Wenninger等人2017 Nucl.Fusion 57 046002）。主要结果是，当强制使用分压器极限时，恒定电功率输出的曲线在R-B_T平面上自身闭合，并且存在可达到的最大功率。一旦达到最佳，R和B_T的进一步增加将不会获得任何好处。该结果对于所有需要辐射SOL来处理功率排出的设备以及存在穿过横隔膜的功率的下限值（例如由于L-H跃迁）的所有那些设备而言，似乎是固有的物理极限。

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  • 来源
    《Nuclear fusion》 |2018年第1期|016032.1-016032.15|共15页
  • 作者

    M. Siccinio; E. Fable; C. Angioni; S. Saarelma; A. Scarabosio; H. Zohm;

  • 作者单位

    Max Planck Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching bei Muenchen, Germany;

    Max Planck Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching bei Muenchen, Germany;

    Max Planck Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching bei Muenchen, Germany;

    Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, United Kingdom;

    Max Planck Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching bei Muenchen, Germany;

    Max Planck Institut fuer Plasmaphysik, Boltzmannstr. 2, 85748 Garching bei Muenchen, 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
  • 关键词

    fusion reactors; tokamak; impurity radiation; reactor scenario;

    机译：聚变反应堆托卡马克杂质辐射反应堆场景;

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