A novel liquid lithium jet-cooled finger-type divertor target concept for fusion power plant application

被引:6
作者
Wang, Zhen [1 ]
Zhang, Shichao [1 ]
Chen, Zhibin [1 ]
Jia, Jiangtao [1 ]
Chao, Chen [1 ]
机构
[1] Chinese Acad Sci, Hefei Inst Phys Sci, Inst Nucl Energy Safety Technol, Hefei 230031, Anhui, Peoples R China
基金
国家重点研发计划; 中国国家自然科学基金;
关键词
divertor target; liquid lithium; finger-type; fusion power plant; ITER; DESIGN;
D O I
10.1088/1741-4326/abe7d1
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
The divertor target is the most thermally loaded plasma-facing component in a foreseen DEMO reactor and beyond, which has to tolerate the peak high heat fluxes of up to similar to 20 MW m(-2) produced by intense plasma bombardment, radiation and nuclear heating. However, none of current designs including water-cooled and helium-cooled concepts can satisfy this requirement. Motivated by the excellent power removal capacity of liquid metal coolant and combined with the structure characteristics of the finger-type helium-cooled target, a novel concept of liquid Li jet-cooled finger-type divertor target for DEMO reactors was proposed in this paper. The performance analysis, including thermal-hydraulics analysis, mechanical analysis and MHD effects analysis, have shown that the proposed design can withstand 20 MW m(-2) heat load because the temperatures of the structural materials remain within the thermal rules and the maximum thermo-mechanical stress in the VM-W thimble is approximately 484 MPa appearing in the round corner, which is below the 3S(m) limit at the corresponding temperature. Moreover, a theoretical and empirical analysis has confirmed that MHD effects on pressure drop and heat transfer is rather limited in the design. The comparison of this new design with other representative designs including water-cooled ITER-like target design and helium-cooled modular jet target design has been made, and the results shows that the proposed liquid Li cooled target design has better performance under 20 MW m(-2) high heat flux and similar to 10 dpa neutron irradiation. Therefore, this design is promising to provide a new option for solving the DEMO reactor divertor heat removal issues. Certainly, a large number of R&D efforts are still needed to ensure the success of this concept, particularly in the areas of materials, fabrication and irradiation.
引用
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页数:9
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共 34 条
  • [1] ASME, 2011, ASME BOILER PRESSURE
  • [2] ITER-like divertor target for DEMO: Design study and fabrication test
    Crescenzi, F.
    Greuner, H.
    Roccella, S.
    Visca, E.
    You, J. H.
    [J]. FUSION ENGINEERING AND DESIGN, 2017, 124 : 432 - 436
  • [3] Development of tungsten divertor components for ITER in Japan
    Ezato, K.
    Suzuki, S.
    Seki, Y.
    Hirayama, T.
    Yamada, H.
    Escourbiac, F.
    Hirai, T.
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 136 : 683 - 689
  • [4] Erosion-corrosion resistance of Reduced Activation Ferritic-Martensitic steels exposed to flowing liquid Lithium
    Favuzza, P.
    Aiello, A.
    Antonelli, A.
    Cuzzani, M.
    Fasano, G.
    Granieri, M.
    Mannori, S.
    Micciche, G.
    Nitti, F. S.
    Tarantino, M.
    Tincani, A.
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 136 : 1417 - 1421
  • [5] The development and testing of the thermal break divertor monoblock target design delivering 20 MWm-2 heat load capability
    Fursdon, M.
    Barrett, T.
    Domptail, F.
    Evans, L. I. M.
    Luzginova, N.
    Greuner, N. H.
    You, J-H
    Li, M.
    Richou, M.
    Gallay, F.
    Visca, E.
    [J]. PHYSICA SCRIPTA, 2017, T170
  • [6] Current status of the technology development on lithium safety handling under IFMIF/EVEDA
    Furukawa, Tomohiro
    Hirakawa, Yasushi
    Kato, Shoichi
    Iijima, Minoru
    Ohtaka, Masahiko
    Kondo, Hiroo
    Kanemura, Takuji
    Wakai, Eiichi
    [J]. FUSION ENGINEERING AND DESIGN, 2014, 89 (12) : 2902 - 2909
  • [7] EXPERIMENTAL STUDIES OF THE THERMAL PERFORMANCE OF GAS-COOLED PLATE-TYPE DIVERTORS
    Hageman, M. D.
    Sadowski, D. L.
    Yoda, M.
    Abdel-Khalik, S. I.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (01) : 228 - 232
  • [8] Design and performance study of the helium-cooled T-tube divertor concept
    Ihli, T.
    Raffray, A. R.
    Abdel-Khalik, S. I.
    Shin, S.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (03) : 249 - 264
  • [9] An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD
    Ihli, T
    Kruessmann, R
    Ovchinnikov, I
    Norajitra, P
    Kuznetsov, V
    Giniyatulin, R
    [J]. FUSION ENGINEERING AND DESIGN, 2005, 75-79 (75-79) : 371 - 375
  • [10] The frontier and perspective for tokamak development
    Li, Jiangang
    Ni, Mingjiu
    Lu, Yu
    [J]. NATIONAL SCIENCE REVIEW, 2019, 6 (03) : 382 - 383