Preliminary structure design and analysis
of CFETR ECRH system launcher

doi:10.16568/j.0254-6086.202403004

Abstract

Abstract: The electron cyclotron resonance heating (ECRH) is an essential auxiliary heating and current driving method for the Chinese Fusion Engineering Testing Reactor (CFETR) to achieve scientific mission. The launcher is one of the core components of the ECRH system. In order to obtain the optimal current drive efficiency of the plasma, the preliminary structure design of ECCD system upper launchers is carried out from five aspects: overall layout, propagation of beam, convergence and launch of beams, neutron shielding, and maintenance scheme. A method of multibeam convergence is adopted for the ECCD launcher, and therefore two sets of 9-beam microwave powers inject into the resonance layer of the plasma through the compact upper port of the CFETR. Using a port-plug structure for the launcher design is beneficial to neutron shield and remote handing maintenance. The effective active cooling schemes for the launcher mirror have been designed via fluid-thermal-solid coupling simulation. The above analysis and design lay a foundation for the further detailed engineering design of ECRH launchers.

Key words: CFETR, ECRH, Launcher, Multibeam convergence, Fluid-thermal-solid coupling simulation

摘要： 电子回旋共振加热(ECRH)是中国聚变工程实验堆(CFETR)实现科学目标必不可少的辅助加热和电流驱动方式。发射天线是电子回旋共振加热系统的核心部件之一。为获得等离子体最佳的电流驱动效率，从发射天线的总体方案、波束的传输、波束的汇聚与发射、中子屏蔽、维护方案等方面对 ECRH 系统顶部发射天线的初步结构进行了设计。ECCD 发射天线通过多波束汇聚方式，在 CFETR 装置紧凑的顶部颈管内，实现了2 组 9 波束微波功率注入至等离子体共振层。发射天线采用颈管插塞式结构设计，有利于中子屏蔽设计和遥操作维护。通过流-热-固耦合仿真分析，为天线发射镜设计了有效的主动冷却方案。本文的分析和设计，为 ECRH 发射天线进一步的详细工程设计奠定了基础。

关键词: CFETR, ECRH, 发射天线, 多波束汇聚, 流-热-固耦合仿真分析

CLC Number:

TL62+ 4

ZHANG Li-yuan, WANG Xiao-jie , WU Da-jun , TANG Yun-ying , WANG Han-lin, LIU Fu-kun. Preliminary structure design and analysis of CFETR ECRH system launcher[J]. Nuclear Fusion and Plasma Physics, 2024, 44(3): 267-274.

张立元, 王晓洁, 吴大俊, 汤允迎, 王瀚林, 刘甫坤 . CFETR ECRH 系统发射天线的初步结构设计与分析 [J]. 核工业西南物理研究院, 2024, 44(3): 267-274.

References

[1] Li J G, Wan Y X. Present state of Chinese magnetic fusion development and future plans [J]. Journal of Fusion Energy, 2019, 38(1): 113.

[2] Zhuang G, Li G Q , Li J, et al. Progress of the CFETR design [J]. Nuclear Fusion, 2019, 59(11): 112010.

[3] Song Y T, Li J G, Wan Y X, et al. Engineering design of the CFETR machine [J]. Fusion Engineering and Design, 2022, 183(Oct.): 113247.

[4] Wagne D, Grünwald G, Leuterer F, et al. Status of the new multi-frequency ECRH system for ASDEX upgrade [J]. Nuclear Fusion, 2008, 48(5): 054006.

[5] Lennholm M, Agarici G, Berger-By G, et al. The ECRH/ECCD system on Tore Supra, a major step towards continuous operation [J]. Nuclear Fusion, 2003, 43(11): 1458.

[6] Cengher M, Lohr J, Simmerling P, et al. Status and plans for the DIII-D ECH/ECCD system [J]. IEEE Transactions on Plasma Science, 2020, 48(6): 1698.

[7] Erckmann V, Brand P, Braune H, et al. Electron cyclotron heating for W7-X: physics and technology [J]. Fusion Science and Technology, 2007, 52(2): 291.

[8] Xu H D, Wang X J, Liu F K, et al. Development and preliminary commissioning results of a long pulse 140 GHz ECRH system on EAST tokamak (invited) [J]. Plasma Science and Technology, 2016, 18(4): 442.

[9] Ramponi G, Farina D, Henderson M A, et al. ITER ECRH-ECCD system capabilities for extended physics applications [J]. Fusion Science and Technology, 2007, 52(2): 193.

[10] Tang Y Y, Wang X J, Zhang L Y, et al. Design status of the ECRH system for CFETR [J]. Fusion Engineering and Design, 2022, 182(Sep.): 113225.

[11] Zhang C, Liu F K, Wang X J, et al. Quasi-optical design of EC H&CD launcher for CFETR [J]. Fusion Engineering and Design, 2021, 166(May): 112295.

[12] Wei W, Wang X J, Li M H, et al. Evaluation of electron cyclotron current drive performance for CFETR [J]. Plasma Science and Technology, 2019, 21(6): 065101.

[13] Zhu P, Li L, Fang Y, et al. MHD analysis on the physics design of CFETR baseline scenarios [J]. Journal of Fusion Energy, 2022, 41(1): 10.

[14] Takahashi K, Abe G, Kajiwara K, et al. Design modification of ITER equatorial EC launcher for electron cyclotron heating and current drive optimization [J]. Fusion Engineering and Design, 2015, 96‒97(Oct.): 602.

[15] Strauss D, Aiello G, Bertizzolo R, et al. Nearing final design of the ITER EC H&CD Upper Launcher [J]. Fusion Engineering and Design, 2019, 146(Part A): 23.

[16] Lu K, Song Y T, Cai L J, et al. First steps of the overall integration design of CFETR [J]. Fusion Engineering and Design, 2021, 173(9‒10): 112928.

[17] Wang H L, Wang X J, Zhang C, et al. Investigation of electron cyclotron wave absorption and current drive in CFETR hybrid scenario plasmas [J]. Plasma Science and Technology, 2023, 25(9): 095101.

[18] Wu Q R, Lu P, Zheng Y, et al. Neutronic analyses of Upper port ECRH antenna system for CFETR [J]. Fusion Engineering and Design, 2021, 162(Jan.): 112078.

[19] Wan Y X, Li J G, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nuclear Fusion, 2017, 57(10): 102009.

[20] 戴淮初，姚达毛. CFETR 偏滤器模块远程遥操作支撑结构设计与仿真分析 [J]. 核聚变与等离子体物理, 2019, 38(3): 323.

[21] Lu P, Wu Q R, Zhang L Y, et al. Operation and shutdown dose rate analysis of CFETR ECRH system [J]. Fusion Engineering and Design, 2020, 159(10): 111751.

[22] Cheng Y, Song Y T, Wu H P, et al. Overview of the CFETR remote handling system and the development progress [J]. Fusion Engineering and Design, 2022, 177(Apr.): 113060.

[23] Zhang L Y, Wang X J, Xu H D, et al. A new design of launcher mirror for EAST electron cyclotron resonance heating system [J]. Fusion Engineering and Design, 2021, 173(2): 112802.

[24] Vagnoni M, Chavan R, Gagliardi M, et al. Thermo-mechanical analysis of an ITER ECH&CD upper launcher mirror [J]. Fusion Engineering and Design, 2018, 136(Part A): 766.

[25] Barabash V. Summary of material properties for structural analysis of the ITER internal components [R]. ITER_D_23HL7T v.3.2, 2009.

[26] Liu S L, Li X, Ma X B, et al. Updated design of water-cooled breeder blanket for CFETR [J]. Fusion Engineering and Design, 2019, 146(7-8): 1716.

Preliminary structure design and analysis of CFETR ECRH system launcher

CFETR ECRH 系统发射天线的初步结构设计与分析

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