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The Fusion Advanced Studies Torus (FAST): a proposal for an ITER satellite facility in support of the development of fusion energy

机译:聚变高级研究环面(FAST):关于ITER卫星设施的提案,以支持聚变能的发展

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摘要

FAST is a new machine proposed to support ITER experimental exploitation as well as to anticipate DEMO relevant physics and technology. FAST is aimed at studying, under burning plasma relevant conditions, fast particle (FP) physics, plasma operations and plasma wall interaction in an integrated way. FAST has the capability to approach all the ITER scenarios significantly closer than the present day experiments using deuterium plasmas. The necessity of achieving ITER relevant performance with a moderate cost has led to conceiving a compact tokamak (R = 1.82 m, a = 0.64 m) with high toroidal field (B_T up to 8.5 T) and plasma current (I_p up to 8 MA). In order to study FP behaviours under conditions similar to those of ITER, the project has been provided with a dominant ion cyclotron resonance heating system (ICRH; 30 MW on the plasma). Moreover, the experiment foresees the use of 6 MW of lower hybrid (LHCD), essentially for plasma control and for non-inductive current drive, and of electron cyclotron resonance heating (ECRH, 4 MW) for localized electron heating and plasma control. The ports have been designed to accommodate up to 10 MW of negative neutral beams (NNBI) in the energy range 0.5-1 MeV. The total power input will be in the 30-40 MW range under different plasma scenarios with a wall power load comparable to that of ITER (P/R ~ 22MWm~(-1)). All the ITER scenarios will be studied: from the reference H mode, with plasma edge and ELMs characteristics similar to the ITER ones (Q up to ≈1.5), to a full current drive scenario, lasting around 170 s. The first wall (FW) as well as the divertor plates will be of tungsten in order to ensure reactor relevantrnoperation regimes. The divertor itself is designed to be completely removable by remote handling. This will allow us to study (in view of DEMO) the behaviour of innovative divertor concepts, such as those based on liquid lithium. FAST is capable of operating with very long pulses, up to 170 s, despite being a copper machine. The magnets initial operation temperature is 30 K, with cooling provided by helium gas. The in vessel components, namely FW and divertor, are actively cooled by pressurized water above 80 ℃. The same water is also used to bake the vacuum vessel. FAST is equipped with ferromagnetic inserts to keep the toroidal field magnet ripple down to 0.3%.
机译:FAST是一种新机器,旨在支持ITER实验开发以及预测DEMO相关的物理和技术。 FAST旨在以集成方式研究在燃烧等离子体相关条件下的快速粒子(FP)物理,等离子体操作和等离子体壁相互作用。与目前使用氘等离子体的实验相比,FAST具有更接近所有ITER情景的能力。以适中的成本获得ITER相关性能的必要性导致构思出紧凑的托卡马克(R = 1.82 m,a = 0.64 m),具有高环形场(B_T至8.5 T)和等离子体电流(I_p至8 MA) 。为了研究类似于ITER的条件下的FP行为,该项目配备了主要的离子回旋共振加热系统(ICRH;等离子30 MW)。此外,该实验还预见将使用6兆瓦的低级混合动力车(LHCD),主要用于等离子体控制和非感应电流驱动,而将电子回旋共振加热(ECRH,4兆瓦)用于局部电子加热和等离子体控制。这些端口的设计可容纳能量范围为0.5-1 MeV的10 MW负中性束(NNBI)。在不同的等离子情景下,总输入功率将在30-40 MW范围内,其壁功率负载可与ITER相比(P / R〜22MWm〜(-1))。将研究所有ITER场景:从参考H模式(等离子边缘和ELM特性与ITER相似)(Q高达≈1.5),到全电流驱动场景,持续约170 s。第一壁(FW)以及分流板将由钨制成,以确保反应堆相关的运行方式。分流器本身设计为可通过远程操作完全移除。这将使我们能够(鉴于DEMO)研究创新的偏滤器概念的行为,例如基于液态锂的偏滤器。尽管是铜制机器,但FAST能够以高达170秒的超长脉冲运行。磁铁的初始工作温度为30 K,由氦气提供冷却。船上的组件,即FW和分流器,通过80℃以上的加压水进行主动冷却。同样的水也用于烘烤真空容器。 FAST配备了铁磁插件,可将环形磁场的磁铁纹波降至0.3%。

著录项

  • 来源
    《Nuclear fusion》 |2010年第9期|P.095005.1-095005.15|共15页
  • 作者单位

    Associazione EURATOM-ENEA, CR ENEA Frascati, C.P. 65, 00044 Frascati, Rome, Italy;

    rnAssociazione EURATOM-ENEA, Consorzio RFX, corso Stati Uniti 4, 35127 Padova, Italy;

    rnAssociazione EURATOM-ENEA, IFP-CNR, via R. Cozzi 53, 20125 Milano, Italy;

    rnAssociazione EURATOM-ENEA, Univ. Napoli Federico II, Via Claudio 21, 80125 Napoli, Italy;

    rnAssociazione EURATOM-ENEA, Univ. Napoli Federico II, Via Claudio 21, 80125 Napoli, Italy;

  • 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);
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  • 正文语种 eng
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