Selected transport studies of a tokamak-based DEMO fusion reactor

被引：19
|
作者：
Fable, E. [1 ]
Wenninger, R. [1 ,2 ]
Kemp, R. [3 ]
机构：
[1] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[2] EUROfus Programme Management Unit, Boltzmannstr 2, D-85748 Garching, Germany
[3] Culham Sci Ctr, EURATOM CCFE Fus Assoc, Abingdon OX14 3DB, Oxon, England
来源：
NUCLEAR FUSION | 2017年 / 57卷 / 02期
关键词：
fusion reactor; tokamak; demo; transport; radiation; turbulence; ARBITRARY COLLISIONALITY; BOOTSTRAP CURRENT; SYSTEMS; PLASMA;
D O I：
10.1088/0029-5515/57/2/022015
中图分类号：
O35 [流体力学]; O53 [等离子体物理学];
学科分类号：
070204 ; 080103 ; 080704 ;
摘要：
As a next-step in the tokamak-based fusion programme, the DEMO fusion reactor is foreseen to produce relevant output electricity, in the order of similar to 500 MW delivered to the network. The scenarios that are being presently investigated consist of a pulsed device, called DEMO1, and a steady-state device, called DEMO2. In this work, which is focused on the pulsed device DEMO1, scenarios are studied from the point of view of core transport, to assess plasma performance and limitations due to core microinstabilities. The role of radiated power, aspect ratio, and height of temperature pedestal are assessed as they impact both core energy and particle transport. Open issues in this framework are also discussed.
引用
收藏
页数：7
相关论文
共 50 条
  • [1] Prospects for Disruption Handling in a Tokamak-Based Fusion Reactor
    Eidietis, N. W.
    FUSION SCIENCE AND TECHNOLOGY, 2021, 77 (7-8) : 738 - 744
  • [2] PROJECTED MATERIALS REQUIREMENTS FOR THE NEXT EUROPEAN TORUS AND FOR LONGTERM TOKAMAK-BASED DEMO FUSION DEVICES
    SCHILLER, P
    NIHOUL, J
    JOURNAL OF NUCLEAR MATERIALS, 1988, 155 : 41 - 48
  • [3] TOKAMAK FUSION REACTOR STUDIES
    WAGNER, CE
    BULLETIN OF THE AMERICAN PHYSICAL SOCIETY, 1978, 23 (07): : 909 - 909
  • [4] FOKKER-PLANCK-TRANSPORT STUDIES OF THE TOKAMAK FUSION TEST REACTOR
    MIRIN, AA
    JASSBY, DL
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 1980, 8 (04) : 503 - 511
  • [5] Development of compact tokamak fusion reactor use cases to inform future transport studies
    Holland, C.
    Bass, E. M.
    Orlov, D. M.
    Mcclenaghan, J.
    Lyons, B. C.
    Grierson, B. A.
    Jian, X.
    Howard, N. T.
    Rodriguez-Fernandez, P.
    JOURNAL OF PLASMA PHYSICS, 2023, 89 (04)
  • [6] Study of neutron generation in the compact tokamak TUMAN-3M in support of a tokamak-based fusion neutron source
    Kornev, V. A.
    Askinazi, L. G.
    Belokurov, A. A.
    Chernyshev, F. V.
    Lebedev, S. V.
    Melnik, A. D.
    Shabelsky, A. A.
    Tukachinsky, A. S.
    Zhubr, N. A.
    NUCLEAR FUSION, 2017, 57 (12)
  • [7] Fusion DEMO reactor design based on nuclear analysis
    Someya, Youji
    Tobita, Kenji
    Hiwatari, Ryoji
    Sakamoto, Yoshiteru
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 1306 - 1312
  • [8] Systems code studies on the optimization of design parameters for a pulsed DEMO tokamak reactor
    Biel, W.
    Beckers, M.
    Kemp, R.
    Wenninger, R.
    Zohm, H.
    FUSION ENGINEERING AND DESIGN, 2017, 123 : 206 - 211
  • [9] Conceptual study of vertical sector transport maintenance for DEMO fusion reactor
    Utoh, Hiroyasu
    Tobita, Kenji
    Someya, Youji
    Takase, Haruhiko
    FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 1409 - 1413
  • [10] CHROMIUM GETTER STUDIES IN THE TOKAMAK FUSION TEST REACTOR
    DYLLA, HF
    LAMARCHE, PH
    BLANCHARD, WR
    BUDNY, RV
    BOODY, FP
    BUSH, CE
    GROEBNER, RJ
    MCCARTHY, PJ
    SIMPKINS, JE
    STRATTON, BC
    ULRICKSON, MA
    JOURNAL OF VACUUM SCIENCE & TECHNOLOGY A-VACUUM SURFACES AND FILMS, 1986, 4 (03): : 1753 - 1757
12345