NUCLEAR FUSION AND PLASMA PHYSICS ›› 2020, Vol. 40 ›› Issue (4): 321-328.DOI: 10.16568/j.0254-6086.202004006
• Nuclear Fusion Engineering and Technology • Previous Articles Next Articles
JIANG Jia-ming1, HUANG Shu-long1, WU Wen-jie1,ZHANG Guo-shu1, LIU Yi2, ZHANG Kai3
Received:
2019-04-08
Revised:
2019-12-17
Online:
2020-12-15
Published:
2021-06-03
Supported by:
江嘉铭1,黄淑龙1,吴文杰1,张国书1,刘 仪2,张 凯3
作者简介:
江嘉铭(1984-),男,江西九江人,工学博士,讲师,从事核反应堆热能工程研究。
基金资助:
CLC Number:
JIANG Jia-ming1, HUANG Shu-long1, WU Wen-jie1,ZHANG Guo-shu1, LIU Yi2, ZHANG Kai3. Numerical research on strengthening secondary flow of tokamak in-vessel coils’ water-cooling pipe joints[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(4): 321-328.
江嘉铭1,黄淑龙1,吴文杰1,张国书1,刘 仪2,张 凯3. 托卡马克真空室内线圈水冷管道接头强化二次流的数值研究[J]. 核聚变与等离子体物理, 2020, 40(4): 321-328.
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URL: https://www.hjby.ac.cn/EN/10.16568/j.0254-6086.202004006
[1] 王淦昌. 21世纪主要能源展望 [J]. 核科学与工程, 1998, 2: 6-17.
[2] Tommasi G D. Plasma magnetic control in Tokamak devices [J]. Journal of Fusion Energy, 2018, 38(3?4): 406-436.
[3] Rogers J G. A polywell fusion reactor designed for net power generation [J]. Journal of Fusion Energy, 2017, 37(2): 1-20.
[4] Wilson, Howard. Edge Localized Modes in Tokamaks [J]. Fusion Science and Technology, 2010, 57(2T): 161-169.
[5] HabibianJ, Salar Elahi A , Salem M K , et al. Edge- localized modes (ELM) modification with transport barrier control in Tokamak by analytical strategies [J]. Journal of Inorganic and Organometallic Polymers and Materials, 2016, 26(5): 1061-1065.
[6] Mcgrath R T. Thermal loads on tokamak plasma-facing components during normal operation and disruptions [J]. Vacuum, 1990, 41(4-6): 1528-1539.
[7] Eich T, Herrmann A, Pautasso G, et al. Power deposition onto plasma facing components in poloidal divertor tokamaks during type-I ELMs and disruptions [J]. J. Nucl. Mater., 2005, 337?339(1-3): 669-676.
[8] Li H, Chen J L, Li J G, et al. High heat load properties of actively cooled tungsten/copper mock-ups by explosive joining [J]. J. Nucl. Mater., 2007, 363: 1226-1230.
[9] Fenstermacher M E, Evans T E, Osborne T H, et al. Suppression of type-I ELMs using a single toroidal row of magnetic field perturbation coils in DIII-D [J]. Nucl. Fusion, 2008, 48(12): 122001.
[10] Fenstermacher M E, Evans T E, Osborne T H, et al. Comparison of edge plasma perturbation during ELM control using one vs. two toroidal rows of RMP coils in ITER similar shaped plasmas on DIII-D [J]. J. Nucl. Mater., 2009, V390?391: 793-796.
[11] Orlov D M, Moyer R A, Evans T E, et al. Suppression of type-I ELMs with reduced RMP coil set on DIII-D [J]. Nucl. Fusion, 2016, 56(3): 036020.
[12] Jakubowski M W, Evans T E, Fenstermacher M E, et al. Overview of the Results on Divertor Heat Loads in RMP Controlled H-mode Plasmas on DIII-D [J]. Nucl. Fusion, 2009, 49(9): 095013.
[13] Jia M, Sun Y, Liang Y, et al. Control of three dimensional particle flux to divertor using rotating RMP in the EAST tokamak [J]. Nucl. Fusion, 2018, 58(4): 046015.
[14] Garzotti L, Belo P, Corrigan G, et al. Integrated core-SOL modelling of fueling, density control and divertor heat loads for the flat-top phase of the ITER H-mode D-T plasma scenarios [J]. Nucl. Fusion, 2019, 59(2): 026006.
[15] Hai Xie, Roman Zagórski, Rui Ding, et al. Numerical analyses for initial-designed CFETR baseline scenario with the integrated COREDIV code [J]. Fusion Eng. Des., 2019, 139: 55-61.
[16] Sigmar D J. Physics problems of fusion reactors [J]. Nucl. Fusion, 1982, 22(1): 123.
[17] Liu Y, Ryan D, Kirk A, et al. Toroidal modelling of RMP response in ASDEX Upgrade: coil phase scan, q95 dependence, and toroidal torques [J]. Nucl. Fusion, 2016, 56(5): 056015.
[18] Rack M, Zeng L, Denner P, et al. Modelling of LHW-induced helical current filaments on EAST: study of an alternative method of applying RMPs [J]. Nucl. Fusion, 2014, 54(6): 064016.
[19] Agarici G, Becoulet M, Nardon E, et al. Design of a resonant magnetic perturbation ELM suppression system for JET [J]. Fusion Eng. Des., 2007, 82(5-14): 974-981.
[20] Ren Qinghua, Wang Yingqiao, Li Qing. Conceptual design and simulation of HL-2A RMP coils power supply [J]. Nuclear Fusion and Plasma Physics, 2015, 48(22): 19-23.
[21] Gobbin M, Li L, Liu Y Q, et al. Runaway electron mitigation by 3D fields in the ASDEX-Upgrade experiment [J]. Plasma Phys. Contr. Fusion, 2018, 60(1): 014036.
[22] Wei Z, Feiran H, Ming Z, et al. Design and implementation of the resonant magnetic perturbations feedback control system for tearing mode suppression on J-TEXT [J]. IEEE Transactions on Nuclear Science, 2018, 65(8): 2344 – 2349.
[23] Kim J, Park G, Bae C, et al. Suppression of edge localized mode crashes by multi-spectral non- axisymmetric fields in KSTAR [J]. Nucl. Fusion, 2017, 57(2): 022001.
[24] Katoh Y, Clark D, Ueda Y, et al. Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors [J]. Fusion Science and Technology, 2017: 1-11.
[25] Henri Greuner, Böswirth B, Barrett T R, et al. Progress in high heat flux testing of European DEMO divertor mock-ups [J]. Fusion Eng. Des., 2018, 12: 021.
[26] Dean W R. Note on the motion of fluid in a curved pipe [J]. SAY Magazine(US), 1927, 4(20): 208-223.
[27] Dean W R, Hurst J M. Note on the motion of fluid in a curved pipe [J]. Mathematika, 1959, 6.
[28] Patankar S V, Pratap V S, Spalding D B. Prediction of turbulent flow in curved pipes [J]. J. Fluid Mech., 2006, 67(3): 583-595.
[29] 陈颖, 邓先和, 丁小江, 等. 强化缩放管内湍流对流换热 [J]. 化工学报, 2004, 55(9): 1528-1531.
[30] Jiang J, Liu Y, Chen Q, et al. Heat dissipation research on the water-cooling channel of HL-2M in-vessel coils [J]. Fusion Eng. Des., 2017, 117: 115-122.
[31] Ali Assoudi, Sabra Habli, NejlaMahjoub Saïd, et al. Experimental and numerical study of an offset jet with different velocity and offset ratios [J]. Engineering Applications of Computational Fluid Mechanics, 2015, 9(1): 490-512.
[32] Kumar R, Dewan A. Assessment of Buoyancy-Corrected Turbulence Models for thermal plumes [J]. Engineering Applications of Computational Fluid Mechanics, 2013, 7(2): 239-249.
[33] Li M, Ni H, Wang R, et al. Comparative simulation research on the stress characteristics of supercritical carbon dioxide jets, nitrogen jets and water jets [J]. Engineering Applications of Computational Fluid Mechanics, 2017, 11(1): 357-370.
[34] Ye Kai, Zhang Yaoli, Sheng Xuanyu, et al. Numerical analysis of the flow behavior in a helically coiled once through steam generator [J]. Nuclear Engineering and Design, 2018, 330: 187-198.
[35] Zhang Haideng, Wu Yun, Li Yinghong. Evaluation of RANS turbulence models in simulating the corner separation of a high-speed compressor cascade [J]. 2015, 9(1): 477–489. |
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