DEMOUNTABLE TOROIDAL FUSION CORE FACILITY FOR TOROIDAL PHYSICS OPTIMIZATION AND FUSION ENGINEERING RESEARCH.

被引:0
|
作者
Bogart, S.L. [1 ]
Wagner, C.E. [1 ]
Krall, N.A. [1 ]
Sedehi, S. [1 ]
Weggel, C.F. [1 ]
Dalessandro, J.A. [1 ]
Seed, T.J. [1 ]
Lund, K.O. [1 ]
机构
[1] EASI, Del Mar, CA, USA, EASI, Del Mar, CA, USA
来源
Fusion Technology | 1986年 / 10卷 / 3 pt 2B期
关键词
TOKAMAK DEVICES - Research;
D O I
10.13182/fst86-a24925
中图分类号
学科分类号
摘要
The Demountable Toroidal Fusion Core (DTFC) concept has been analyzed for the Inductively Heated Tokamak (IHT), the Spherical Tokamak (ST), and the Reversed Field Pinch (RFP) for Fusion Engineering Research Facility (FERF) applications. Each of these confinement concepts is viewed as a 'core' that is inserted into a surrounding machine envelope including, for example, the outboard toroidal field coil turns, the major poloidal equilibrium coils, blanket and materials testing stations, and a tension-suppression system (precompression) that provides mechanical integrity during the ignition and burn phases. Parametric systems analysis reveals that DTFC FERF operation is possible for all three confinement configurations with the IHT being the most costly and technologically challenging and the RFP being the least costly and, perhaps, least technologically challenging.
引用
收藏
页码:1404 / 1411
相关论文
共 50 条
  • [21] SIGNAL ANALYSIS OF FLUCTUATIONS IN TOROIDAL FUSION PLASMAS
    BELL, JD
    HARRIS, JH
    DUNLAP, JL
    CROCKER, NA
    PARE, VK
    REVIEW OF SCIENTIFIC INSTRUMENTS, 1993, 64 (09): : 2428 - 2433
  • [22] PARTICLE AND IMPURITY CONTROL IN TOROIDAL FUSION DEVICES
    WOOTTON, AJ
    JOURNAL OF VACUUM SCIENCE & TECHNOLOGY A-VACUUM SURFACES AND FILMS, 1986, 4 (04): : 1918 - 1932
  • [23] Edge ambipolar potential in toroidal fusion plasmas
    Spizzo, G.
    Vianello, N.
    White, R. B.
    Abdullaev, S. S.
    Agostini, M.
    Cavazzana, R.
    Ciaccio, G.
    Puiatti, M. E.
    Scarin, P.
    Schmitz, O.
    Spolaore, M.
    Terranova, D.
    PHYSICS OF PLASMAS, 2014, 21 (05)
  • [24] SUPERCONDUCTING MAGNETS FOR TOROIDAL FUSION-REACTORS
    HAUBENREICH, PN
    IEEE TRANSACTIONS ON MAGNETICS, 1981, 17 (01) : 31 - 37
  • [25] BLANKET REPLACEMENT IN TOROIDAL FUSION REACTORS.
    Mitchell, J.T.D.
    1978,
  • [26] Evaluation of AC losses in toroidal field magnets in the China Fusion Engineering Test Reactor
    Xu, Weiwei
    Liu, Xufeng
    Zheng, Jinxing
    Du, Shuangsong
    Ni, Xiaojun
    Zou, Chunlong
    Li, Ming
    FUSION ENGINEERING AND DESIGN, 2022, 181
  • [27] REMOTE OPERATIONS IN A FUSION ENGINEERING RESEARCH FACILITY (FERF)
    DOGGETT, JN
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 731 - 732
  • [28] Core size effects of laser fusion subcritical research reactor for fusion engineering research
    Iwamoto, A.
    Kodama, R.
    NUCLEAR FUSION, 2021, 61 (11)
  • [29] ROTATING LIQUID BLANKET FOR A TOROIDAL FUSION-REACTOR
    MOIR, RW
    FUSION ENGINEERING AND DESIGN, 1987, 5 (03) : 269 - 272
  • [30] CURRENT EXPECTATIONS FOR FUSION POWER FROM TOROIDAL MACHINES
    MILLS, RG
    IEEE TRANSACTIONS ON POWER APPARATUS AND SYSTEMS, 1974, PA93 (06): : 1805 - 1809