• 中文核心期刊要目总览
  • 中国科技核心期刊
  • 中国科学引文数据库(CSCD)
  • 中国科技论文与引文数据库(CSTPCD)
  • 中国学术期刊文摘数据库(CSAD)
  • 中国学术期刊(网络版)(CNKI)
  • 中文科技期刊数据库
  • 万方数据知识服务平台
  • 中国超星期刊域出版平台
  • 国家科技学术期刊开放平台
  • 荷兰文摘与引文数据库(SCOPUS)
  • 日本科学技术振兴机构数据库(JST)
  • Abstract:
    ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p-11B fusion, establish spherical torus/tokamak experimental scaling laws at 10’s keV ion temperature, and provide a design basis for subsequent experiments to test and realize the p-11B fusion burning plasma. Based on 0-dimensional (0-D) system design and 1.5-dimensional transport modelling analyses, the main target parameters of EHL-2 have been basically determined, including the plasma major radius, R0, of 1.05 m, the aspect ratio, A, of 1.85, the maximum central toroidal magnetic field strength, B0, of 3 T, and the plasma toroidal current, Ip, of 3 MA. The main heating system will be the neutral beam injection at a total power of 17 MW. In addition, 6 MW of electron cyclotron resonance heating will serve as the main means of local current drive and MHD instabilities control. The physics design of EHL-2 is focused on addressing three main operating scenarios, i.e., (1) high ion temperature scenario, (2) high-performance steady-state scenario and (3) high triple product scenario. Each scenario will integrate solutions to different important issues, including equilibrium configuration, heating and current drive, confinement and transport, MHD instability, p-11B fusion reaction, plasma-wall interactions, etc. Beyond that, there are several unique and significant challenges to address, including
    ● establish a plasma with extremely high core ion temperature (Ti,0 > 30 keV), and ensure a large ion-to-electron temperature ratio (Ti,0/Te,0 > 2), and a boron concentration of 10%‒15% at the plasma core;
    ● realize the start-up by non-inductive current drive and the rise of MA-level plasma toroidal current. This is because the volt-seconds that the central solenoid of the ST can provide are very limited;
    ● achieve divertor heat and particle fluxes control including complete detachment under high P/R (> 20 MW/m) at relatively low electron densities.
    This overview will introduce the advanced progress in the physics design of EHL-2.

     

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