Tritium recovery in ITER by radiative plasma terminations

被引:27
|
作者
Whyte, DG
Davis, JW
机构
[1] Univ Wisconsin, Madison, WI 53706 USA
[2] Univ Toronto, Inst Aerosp Studies, N York, ON M3H 5T6, Canada
关键词
tritium; desorption; hydrogen inventory; ablation;
D O I
10.1016/j.jnucmat.2004.10.134
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Planned radiative plasma terminations are examined as a method to recover tritium from plasma-deposited layers in the ITER tokamak. The technique exploits the high energy density of the ITER plasma, which is converted into a quasi-uniform radiation pulse by massive impurity injection that benignly terminates the plasma discharge. The radiation pulse transiently heats all plasma-viewing surfaces in order to desorb the tritium, which is released into the vessel and recovered by pumping. Calculations indicate significant tritium removal at reduced plasma current, similar to 6-10 MA, indicating the possibility of routine T recovery during the current rampdown phase of each discharge or during low current tritium recovery discharges. (c) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:560 / 564
页数:5
相关论文
共 50 条
  • [31] Tritium inventories and tritium safety design principles for the fuel cycle of ITER
    Cristescu, I. R.
    Cristescu, I.
    Doerri, L.
    Glugla, M.
    Murdoch, D.
    NUCLEAR FUSION, 2007, 47 (07) : S458 - S463
  • [32] Combined scheduling model to optimize tritium inventory in tritium plant of ITER
    Lee, Suh-Young
    Lee, Jae-Uk
    Chang, Min Ho
    Ha, Jin-Kuk
    Lee, In-Beum
    Lee, Min-Kyung
    Lee, Euy Soo
    FUSION ENGINEERING AND DESIGN, 2021, 169
  • [33] The effect of pulse operation on tritium permeation and inventory in ITER's plasma-facing components
    Housiadas, C
    Perujo, A
    FUSION TECHNOLOGY, 2000, 37 (01): : 68 - 73
  • [34] Tritium analysis for the european HCPB TBM in ITER
    Meyder, R.
    Boccaccini, L. V.
    Bekris, N.
    21ST IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING - SOFE 05, 2006, : 267 - 270
  • [35] DEVELOPMENT OF TRITIUM TRANSPORT PACKAGE FOR ITER SUPPLY
    Lee, Sanghoon
    Lee, Min-Soo
    Lee, Ju-Chan
    Choi, Woo-Seok
    Seo, Ki-Seog
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE (PVP-2011), VOL 7, 2012, : 387 - 393
  • [36] Problem of tritium for the international fusion reactor (ITER)
    Inst Biofiziki, Moscow, Russia
    Atomnaya Energiya, 1995, 78 (04): : 290 - 293
  • [37] Tritium inventory and permeation in the ITER breeding blanket
    Violante, V
    Tosti, S
    Sibilia, C
    Felli, F
    Casadio, S
    Alvani, C
    FUSION ENGINEERING AND DESIGN, 2000, 49-50 : 697 - 701
  • [38] Wet scrubber technology for tritium confinement at ITER
    Perevezentsev, A. N.
    Andreev, B. M.
    Rozenkevich, M. B.
    Pak, Yu. S.
    Ovcharov, A. V.
    Marunich, S. A.
    FUSION ENGINEERING AND DESIGN, 2010, 85 (7-9) : 1206 - 1210
  • [39] Tritium transfers evaluation on ITER HCLL TBM
    Gastaldi, O.
    Aizes, P.
    Gabriel, F.
    Salavy, J. F.
    Giancarli, L.
    FUSION SCIENCE AND TECHNOLOGY, 2008, 54 (01) : 101 - 106
  • [40] THE PROBLEM OF TRITIUM FOR THE INTERNATIONAL THERMONUCLEAR REACTOR ITER
    FOMIN, GV
    ATOMIC ENERGY, 1995, 78 (04) : 287 - 290