Optimization of the snowflake divertor for power and particle exhaust on NSTX-U

被引:10
|
作者
Vail, P. J. [1 ]
Izacard, O. [1 ]
Kolemen, E. [1 ]
机构
[1] Princeton Univ, Dept Mech & Aerosp Engn, Princeton, NJ 08544 USA
基金
美国能源部;
关键词
NSTX-U; snowflake divertor; cryopump; UEDGE; DIII-D; TRANSPORT;
D O I
10.1016/j.nme.2019.03.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In this paper, simple analytical modeling and numerical simulations performed with the multi-fluid edge transport code UEDGE are used to identify optimal snowflake divertor (SFD) configurations for heat flux mitigation and sufficient cryopumping performance on the National Spherical Torus eXperiment Upgrade (NSTX-U). A model is presented that describes the partitioning of sheath-limited SOL power and particle exhaust in the SFD as a result of diffusive transport to multiple activated strike points. The model is validated against UEDGE predictions and used to analyze a database of 70 SFD-minus equilibria. The optimal location for the entrance to a divertor cryopumping system on NSTX-U is computed for enabling sufficient pumping performance with acceptable power loading in a variety of SFD-minus configurations. UEDGE simulations of one promising equilibrium from the database indicate that a significant redistribution of power to the divertor legs occurs as a result of neutral particle removal near one of the SFD-minus strike points in the outboard scrape-off layer. It is concluded that pump placement at the optimal location is advantageous as the large number of compatible equilibria reduces the precision required of real-time SFD configuration control systems and enables acceptable divertor solutions even if UEDGE-predicted power redistribution slightly reduces the achievable pumping performance.
引用
收藏
页码:516 / 523
页数:8
相关论文
共 50 条
  • [1] Design and simulation of the snowflake divertor control for NSTX-U
    Vail, P. J.
    Boyer, M. D.
    Welander, A. S.
    Kolemen, E.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2019, 61 (03)
  • [2] A study of X-divertor in NSTX-U with SOLPS simulations
    Chen, Zhong-Ping
    Kotschenreuther, Mike
    Mahajan, Swadesh
    Gerhardt, Stefan
    NUCLEAR FUSION, 2018, 58 (03)
  • [3] Conceptual design of a divertor Thomson scattering diagnostic for NSTX-U
    McLean, A. G.
    Soukhanovskii, V. A.
    Allen, S. L.
    Carlstrom, T. N.
    LeBlanc, B. P.
    Ono, M.
    Stratton, B. C.
    REVIEW OF SCIENTIFIC INSTRUMENTS, 2014, 85 (11)
  • [4] The effect of gas injection location on a lithium vapor box divertor in NSTX-U
    Emdee, E. D.
    Goldston, R. J.
    NUCLEAR FUSION, 2023, 63 (09)
  • [5] Error field impact on mode locking and divertor heat flux in NSTX-U
    Ferraro, N. M.
    Park, J-K
    Myers, C. E.
    Brooks, A.
    Gerhardt, S. P.
    Menard, J. E.
    Munaretto, S.
    Reinke, M. L.
    NUCLEAR FUSION, 2019, 59 (08)
  • [6] Exploration of magnetic perturbation effects on advanced divertor configurations in NSTX-U
    Frerichs, H.
    Schmitz, O.
    Waters, I.
    Canal, G. P.
    Evans, T. E.
    Feng, Y.
    Soukhanovskii, V. A.
    PHYSICS OF PLASMAS, 2016, 23 (06)
  • [7] A snowflake divertor: a possible solution to the power exhaust problem for tokamaks
    Ryutov, D. D.
    Cohen, R. H.
    Rognlien, T. D.
    Umansky, M. V.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2012, 54 (12)
  • [8] Assessment of equilibrium field coil misalignments on the divertor footprints in NSTX-U
    Munaretto, S.
    Evans, T. E.
    Ferraro, M.
    Orlov, D. M.
    Trevisan, G. L.
    Wu, W.
    NUCLEAR FUSION, 2019, 59 (07)
  • [9] Optimization of lithium vapor box divertor evaporator location on NSTX-U using SOLPS-ITER
    Emdee, E. D.
    Goldston, R. J.
    Khodak, A.
    Maingi, R.
    NUCLEAR FUSION, 2024, 64 (08)
  • [10] Modeling divertor concepts for spherical tokamaks NSTX-U and ST-FNSF
    Meier, E. T.
    Gerhardt, S.
    Menard, J. E.
    Rognlien, T. D.
    Soukhanovskii, V. A.
    NUCLEAR FUSION, 2015, 55 (08)