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Actuator and diagnostic requirements of the ITER Plasma Control System

机译:ITER等离子控制系统的执行器和诊断要求

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摘要

The ITER Plasma Control System (PCS) requires an extensive set of about 50 diagnostic systems to measure the plasma response and about 20 actuators to act on the plasma to carry out its control functions. The specifications and real limitations of the actuators and diagnostics are being assessed as part of the ongoing conceptual design of the PCS to understand the potential impact on plasma control. The actuators include magnetic coils (central solenoid (CS), poloidal field (PF), vertical stability (VS), edge localized mode (ELM), correction coils (CC)), heating and current drive (electron cyclotron (EC), ion cyclotron (IC), neutral beam injection (NB1), and possibly lower hybrid (LH)), glow discharge cleaning, fueling and impurity gas and pellet injection, vacuum pumping, and disruption mitigation systems. Diagnostic systems are prioritized according to their role in machine protection (MP), basic control (BC), advanced control (AC), and physics studies (PS). At the conceptual design phase, detailed control algorithms do not yet need to be specified, but conceptual solutions must be chosen that satisfy the PCS requirements for control within the real constraints of the diagnostics and actuators. The feasibility of the chosen solutions must be proven either through established control schemes on existing machines or through an R&D program to develop them before they will be required on ITER. The diagnostic and actuator requirements of the PCS will evolve from first plasma through the high performance DT phase. A comparison is made of the expected requirements to control vertical stability, sawteeth, neoclassical tearing modes (NTMs), edge localized modes (ELMs), error fields, resistive wall modes (RWMs), Alfven eigenmodes, and disruptions with the ITER baseline actuator and diagnostic specifications.
机译:ITER等离子体控制系统(PCS)需要大量的约50个诊断系统来测量等离子体响应,并需要约20个执行器对等离子体起作用以执行其控制功能。作为PCS正在进行的概念设计的一部分,正在评估执行器和诊断程序的规格和实际限制,以了解对血浆控制的潜在影响。执行器包括电磁线圈(中央螺线管(CS),极场(PF),垂直稳定性(VS),边缘局部模式(ELM),校正线圈(CC)),加热和电流驱动(电子回旋加速器(EC),离子回旋加速器(IC),中性束注入(NB1)以及可能的低级混合动力(LH)),辉光放电清洁,加注燃料和杂质气体和颗粒注入,真空泵和扰动缓解系统。根据诊断系统在机器保护(MP),基本控制(BC),高级控制(AC)和物理研究(PS)中的作用来确定其优先级。在概念设计阶段,尚不需要指定详细的控制算法,但必须选择在诊断和执行器的实际限制内满足PCS要求的概念解决方案。所选解决方案的可行性必须通过在现有机器上建立控制方案或通过研发计划进行开发来证明,然后才能在ITER上使用。 PCS的诊断和执行器要求将从最初的等离子体发展到高性能DT阶段。比较了控制垂直稳定性,锯齿,新古典撕裂模式(NTM),边缘局部化模式(ELM),误差场,电阻墙模式(RWM),Alfven本征模式以及ITER基线执行器和扰动的预期要求诊断规范。

著录项

  • 来源
    《Fusion Engineering and Design》 |2012年第12期|1900-1906|共7页
  • 作者单位

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    Japan Atomic Energy Agency, Naka, Ibaraki-ken 311-0193, Japan;

    Association EURATOM - Confederation Suisse, Ecole Polytechnique Federate de Lausanne (EPFL), CRPP, Lausanne CH-1015, Switzerland;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

    ITER Organization, St. Paul-lez-Durance 13115, France;

  • 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 control; ITER; tokamak;

    机译:等离子控制ITER;托卡马克;
  • 入库时间 2022-08-18 00:39:17

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