Power balance in the ITER plasma and divertor

被引:9
|
作者
Post, DE
Braams, B
Mandrekas, J
Stacey, W
Putvinskaya, N
机构
[1] NYU,COURANT INST,NEW YORK,NY
[2] GEORGIA INST TECHNOL,ATLANTA,GA 30332
[3] ITER SAN DIEGO JOINT WORK SITE,SAIC,SAN DIEGO,CA
关键词
D O I
10.1002/ctpp.2150360226
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
It is planned to use atomic processes to spread out most of the heating power over the first wall and side walls to reduce the heat loads on the plasma facing components in ITER to similar to 50 MW. Calculations indicate that there will be 100 MW in bremstrahlung radiation from the plasma center, 50 MW of radiation from the plasma edge inside the separatrix and 100 MW of radiation from the scrape-off layer and divertor plasma, leaving 50 MW of power to be deposited on the divertor plates. The radiation losses are enhanced by the injection of impurities such as Neon or Argon at acceptably low levels (similar to 0.1 % Argon, etc.).
引用
收藏
页码:240 / 244
页数:5
相关论文
共 50 条
  • [41] The impact of ELMs on the ITER divertor
    Leonard, AW
    Herrmann, A
    Itami, K
    Lingertat, J
    Loarte, A
    Osborne, TH
    Suttrop, W
    JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 109 - 117
  • [42] Fabrication of divertor cassette for ITER
    Sanguinetti, Gian Paolo
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2008, 53 (10): : 637 - +
  • [43] ITER DIVERTOR SYSTEM INTEGRATION
    Martin, A.
    Andrew, P.
    Jokinen, T.
    Komarov, V.
    Kukushkin, A.
    Loarte, A.
    Maruyama, S.
    Merola, M.
    Palmer, J.
    Pearce, R.
    Pick, M.
    Pitts, R.
    Walker, C.
    FUSION SCIENCE AND TECHNOLOGY, 2009, 56 (01) : 65 - 69
  • [44] Divertor impurity monitor for ITER
    Sugie, T
    Ogawa, H
    Katsunuma, J
    Maruo, M
    Ebisawa, K
    Ando, T
    Kita, Y
    Kasai, S
    DIAGNOSTICS FOR EXPERIMENTAL THERMONUCLEAR FUSION REACTORS 2, 1998, : 327 - 336
  • [45] Synthesized intensity of emission lines of hydrogen isotopes and impurities in the ITER divertor plasma
    Iwamae, A.
    Sugie, T.
    Ogawa, H.
    Kusama, Y.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2011, 53 (04)
  • [46] Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components
    Escourbiac, F.
    Constans, S.
    Vignal, N.
    Cantone, V.
    Richou, M.
    Durocher, A.
    Riccardi, B.
    Bobin, I.
    Jouvelot, J. L.
    Merola, M.
    FUSION ENGINEERING AND DESIGN, 2009, 84 (2-6) : 747 - 751
  • [47] Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities
    Wright, G. M.
    Kleyn, A. W.
    Alves, E.
    Alves, L. C.
    Barradas, N. P.
    van Rooij, G. J.
    van Lange, A. J.
    Shumack, A. E.
    Westerhout, J.
    Al, R. S.
    Vijvers, W. A. J.
    de Groot, B.
    de Pol, M. J. van
    van der Meiden, H. J.
    Rapp, J.
    Cardozo, N. J. Lopes
    JOURNAL OF NUCLEAR MATERIALS, 2009, 390-91 : 610 - 613
  • [48] Development of the plasma facing components for the dome-liner component of the ITER divertor
    Luconi, U
    Di Marco, A
    Federici, A
    Grattarola, A
    Gualco, G
    Larrea, JM
    Merola, M
    Ozzano, C
    Pasquale, G
    FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 271 - 276
  • [49] SOLPS-ITER Modeling of the Alcator C-Mod Divertor Plasma
    Dekeyser, Wouter
    Bonnin, Xavier
    Lisgo, Steven W.
    Pitts, Richard A.
    Brunner, Dan
    Labombard, Brian
    Terry, Jim L.
    PLASMA AND FUSION RESEARCH, 2016, 11
  • [50] Repair of manufacturing defects in the armor of plasma facing units of the ITER Divertor Dome
    Litunovsky, Nikolay
    Alekseenko, Evgeny
    Kuznetsov, Vladimir
    Lyanzberg, Dmitriy
    Makhankov, Aleksey
    Rulev, Roman
    FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 1739 - 1743