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Conceptual design study of the moderate size superconducting spherical tokamak power plant

机译:中型超导球形托卡马克发电厂的概念设计研究

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摘要

A new conceptual design of the superconducting spherical tokamak (ST) power plant was proposed as an attractive choice for tokamak fusion reactors. We reassessed a possibility of the ST as a power plant using the conservative reactor engineering constraints often used for the conventional tokamak reactor design. An extensive parameters scan which covers all ranges of feasible superconducting ST reactors was completed, and five constraints which include already achieved plasma magnetohydrodynamic (MHD) and confinement parameters in ST experiments were established for the purpose of choosing the optimum operation point. Based on comparison with the estimated future energy costs of electricity (COEs) in Japan, cost-effective ST reactors can be designed if their COEs are smaller than 120 mills kW~(-1) h~(-1) ($2013). We selected the optimized design point: A - 2.0and R_p = 5.4 m after considering the maintenance schemeandTF ripple. A self-consistent free-boundary MHD equilibrium and poloidal field coil configuration of the ST reactor were designed by modifying the neutral beam injection system and plasma profiles. The MHD stability of the equilibrium was analysed and a ramp-up scenario was considered for ensuring the new ST design. The optimized moderate-size ST power plant conceptual design realizes realistic plasma and fusion engineering parameters keeping its economic competitiveness against existing energy sources in Japan.
机译:提出了超导球形托卡马克(ST)电厂的新概念设计,作为托卡马克聚变反应堆的诱人选择。我们使用通常用于常规托卡马克反应堆设计的保守反应堆工程约束条件,重新评估了意法半导体作为发电厂的可能性。完成了涵盖可行的超导ST反应器所有范围的广泛参数扫描,并建立了五个约束条件,包括已在ST实验中实现的等离子体磁流体动力学(MHD)和约束参数,以选择最佳运行点。根据与日本预计的未来电力能源成本(COE)的比较,如果COE小于120千瓦kW〜(-1)h〜(-1)(2013年),则可以设计出具有成本效益的ST反应堆。在考虑了维护方案和TF纹波之后,我们选择了优化的设计点:A-2.0和R_p = 5.4 m。通过修改中性束注入系统和等离子体分布图,设计了ST反应器的自洽自由边界MHD平衡和极向场线圈构型。分析了平衡的MHD稳定性,并考虑了加速方案以确保新的ST设计。经过优化的中型ST电厂概念设计可实现逼真的等离子和聚变工程参数,从而保持其相对于日本现有能源的经济竞争力。

著录项

  • 来源
    《Nuclear fusion》 |2015年第6期|063036.1-063036.14|共14页
  • 作者单位

    The University of Tokyo, Bunkyo-ku? Tokyo 113-0032, Japan;

    The University of Tokyo, Bunkyo-ku? Tokyo 113-0032, Japan;

    Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan;

    Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan;

    Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan;

    Japan Atomic Energy Agency, Rokkasho, Aomori 039-3212, Japan;

    Princeton Plasma Physics Laboratory, 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

    spherical tokamak; reactor design; system design; plasma physics design; ramp-up scenario;

    机译:球形托卡马克反应堆设计;系统设计;等离子物理设计;加速方案;
  • 入库时间 2022-08-18 00:42:33

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