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Helium experiments on Alcator C-Mod in support of ITER early operations

机译:在Alter C-Mod上进行氦气实验以支持ITER的早期运营

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摘要

Helium majority experiments on Alcator C-Mod were performed to compare with deuterium discharges, and inform ITER early operations. ELMy H-modes were produced with a special plasma shape at B_T = 5.3 T, I_P = 0.9 MA, at q_(95) ~ 3.8. The He fraction ranged over, n_(He,L)_L = 0.2-0.4, with n_(D,L)_L = 0.15-0.26, compared to D plasmas with n_(D,L)_L = 0.85-0.97. The power to enter the H-mode in He was found to be greater than ~2 times that for D discharges, in the low density region <1.4 x 10~(20)/m~3. However, it appears to follow the D threshold for higher densities. The stored energies in the He discharges were about 80% of those in D, and about 40% higher net power was required to sustain them compared to D. Global particle confinement times for tungsten of T_w~*/T_E - 4 were obtained with ELMy H-modes in He, however accumulation occurred when the ELMs were irregular and infrequent. The electron temperatures and densities in the pedestal were similar between D and He discharges, and the ∆T_e/T_e and ∆n_e_e values were similar or larger in He than D. The higher net power required to access the H-mode, and sustain it in flattop, for He discharges in C-Mod, imply some limitations for He operation in ITER.
机译:在Alcator C-Mod上进行了氦气多数实验,以与氘气排放进行比较,并告知ITER早期操作。 ELMy H-modes在b_T = 5.3 T,I_P = 0.9 MA,q_(95)〜3.8时具有特殊的等离子体形状。与n_(D,L)/ n_L = 0.85-0.97的D等离子体相比,He分数的范围为n_(He,L)/ n_L = 0.2-0.4,其中n_(D,L)/ n_L = 0.15-0.26 。在<1.4 x 10〜(20)/ m〜3的低密度区域,发现在He中进入H模式的功率大于D放电的功率的约2倍。但是,对于更高的密度,它似乎遵循D阈值。与D相比,He放电中存储的能量大约是D中的能量的80%,维持它们所需的净功率大约高出40%。用ELMy获得了T_w〜* / T_E-4钨的整体粒子约束时间He中的H型,但是当ELM不规则且不频繁时会发生积累。在D和He放电之间,基座的电子温度和密度相似,并且He中的∆T_e / T_e和∆n_e / n_e值与D相似或更大。进入H模式所需的净功率更高,并且将其维持在平顶状态,因为He在C-Mod中放电,这暗示着ITER中He操作的一些限制。

著录项

  • 来源
    《Nuclear fusion》 |2018年第5期|056007.1-056007.14|共14页
  • 作者单位

    Princeton Plasma Physics Laboratory, Princeton, New Jersey, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Oak Ridge National Laboratory, Oak Ridge, Tennessee, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts, United States of America;

    Princeton Plasma Physics Laboratory, Princeton, New Jersey, United States of America;

    @;

  • 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

    tokamak; helium discharge; ITER; ELMy H-mode;

    机译:托卡马克氦气放电ITER;ELMy H模式;

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