Influence of CFETR blanket equivalent resistivity on the growth rate of plasma vertical displacement

doi:10.16568/j.0254-6086.202201015

Abstract

Abstract: 基于CFETR工程设计，使用TOKSYS建立了CFETR极向场线圈、真空室壁和包层结构的等效二维模型。在三种平衡的等离子体位形下，分析了包层结构整体等效电阻率和极向不同位置的等效电阻率对等离子体垂直位移增长率的影响。结果表明，垂直位移增长率随着包层整体等效电阻率的增加近似线性增大；降低极向±60°附近的等效电阻率，能减小垂直位移增长率。

Key words: CFETR, Growth rate of vertical displacement, TOKSYS, Equivalent resistivity

摘要： 基于CFETR工程设计，使用TOKSYS建立了CFETR极向场线圈、真空室壁和包层结构的等效二维模型。在三种平衡的等离子体位形下，分析了包层结构整体等效电阻率和极向不同位置的等效电阻率对等离子体垂直位移增长率的影响。结果表明，垂直位移增长率随着包层整体等效电阻率的增加近似线性增大；降低极向±60°附近的等效电阻率，能减小垂直位移增长率。

关键词: CFETR, 垂直位移增长率, TOKSYS, 等效电阻率

CLC Number:

O534⁺.2

CHEN Dong, YE Min-you, MAO Shi-feng, CHEN Shu-liang, LI Hang, HUANG Tai-hao. Influence of CFETR blanket equivalent resistivity on the growth rate of plasma vertical displacement[J]. Nuclear Fusion and Plasma Physics, 2022, 42(1): 91-96.

陈东, 叶民友, 毛世峰, 陈树亮, 李航, 黄泰豪. CFETR包层等效电阻率对等离子体垂直位移增长率的影响[J]. 核聚变与等离子体物理, 2022, 42(1): 91-96.

References

[1] Wan Y, Li J, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nucl. Fusion, 2017, 57(10): 102009.
[2] Zhuang G, Li G Q, Li J, et al. Progress of the CFETR design [J]. Nucl. Fusion, 2019, 59(11): 112010.
[3] Doyle E J, Houlberg W A, Kamada Y, et al. Progress in the ITER physics basischapter 2: Plasma confinement and transport [J]. Nucl. Fusion, 2007, 47(6): S18-S127.
[4] 袁保山. 托卡马克装置工程基础 [M]. 北京: 原子能出版社, 2011.
[5] Xu K, Ye M Y, Song Y T, et al. Neutronic analyses for CFETR with modular helium cooled lithium ceramic blanket [C]. 25th International Conference on Nuclear Engineering. 2017.
[6] Lu Y, Xu K, Ye M, et al. Neutronics analysis of helium cooled ceramic breeder blanket with s-shaped lithium zone and cooling plate for CFETR [J]. IEEE Transactions on Plasma Science, 2018, 46(5): 1471-1476.
[7] Favez J-Y. Enhancing the control of tokamaks via a continuous nonlinear control law [R]. École Polytechnique Fédérale de Lausanne (EPFL), 2004.
[8] 谭胜均, 张洋, 叶民友, 等. EAST上由垂直不稳定性引发破裂的分析与预测 [J]. 核聚变与等离子体物理, 2019, 39(2): 104-111.
[9] 刘磊. EAST垂直位移被动稳定及主动控制模拟与实验研究 [D]. 合肥: 中国科学技术大学, 2015.
[10] Humphreys D A, Casper T A, Eidietis N, et al. Experimental vertical stability studies for ITER performance and design guidance [J]. Nucl. Fusion, 2009, 49(11): 115003.
[11] Liu G J, Wan B N, Qian J P, et al. Effect of passive plates on vertical instability in the EAST tokamak [J]. Chinese Physics B, 2012, 21(8): 085201.
[12] Li B, Liu L, Guo Y, et al. Preliminary assessment of vertical instability with blanket in CFETR [J]. Fusion Engineering and Design, 2019, 148: 111295.
[13] Humphreys D, Ferron J, Bakhtiari M, et al. Development of ITER-relevant plasma control solutions at DIII-D [J]. Nucl. Fusion, 2007, 47(8): 943.
[14] Humphreys D A, Ferron J R, Hyatt A W, et al. DIII-D Integrated plasma control solutions for ITER and next-generation tokamaks [J]. Fusion Engineering and Design, 2008, 83(2-3): 193-197.
[15] Xiao B J, Yuan Q P, Humphreys D A, et al. Recent plasma control progress on EAST [J]. Fusion Engineering and Design, 2012, 87(12): 1887-1890.
[16] 张卡. 基于刚体模型的EAST等离子体控制仿真模拟 [D]. 合肥: 中国科学院合肥物质科学研究院, 2007.
[17] Hahn S-h, Welander A S, Yoon S W, et al. Progress and improvement of KSTAR plasma control using model-based control simulators [J]. Fusion Engineering and Design, 2014, 89(5): 542-547.
[18] Walker M L, Humphreys D A, Sammuli B, et al. Development environments for tokamak plasma control [C]. IEEE 26th Symposium on Fusion Engineering, 2015.
[19] Humphreys D A, Walker M L, Leuer J A. Minimal plasma response models for design of tokamak equilibrium controllers with high dynamic accuracy [C]. 41st Annual Meet of Division of PPAPS, 1999.
[20] Walker M L, Humphreys D A. Valid coordinate systems for linearized plasma shape response models in tokamaks [J]. Fusion Science and Technology, 2006, 50(4): 473-489.
[21] Luo Z P, Xiao B J, Leuer J A, et al. Eddy calculation and vacuum field reconstruction on EAST [J]. Plasma Science & Technology, 2011, 13(2): 145-152.
[22] Coutlis A, Bandyopadhyay I, Lister J B, et al. Measurement of the open loop plasma equilibrium response in TCV [J]. Nucl. Fusion, 1999, 39(5): 663-683.
[23] Sharma A S. Tokamak modelling and control [D]. University of London, 2002.
[24] Chen S L, Villone F, Xiao B J, et al. Equivalent axisymmetric plasma response models of EAST [J]. Plasma Phys. Contr. Fusion, 2016, 58(2): 025017.
[25] 陈树亮. 基于被动导体结构三维模型的EAST垂直不稳定性研究 [D]. 北京: 中国科学院大学, 2016.
[26] Li J, Wan Y. Present state of chinese magnetic fusion development and future plans [J]. Journal of Fusion Energy, 2019, 38(1): 113-124.

Influence of CFETR blanket equivalent resistivity on the growth rate of plasma vertical displacement

CFETR包层等效电阻率对等离子体垂直位移增长率的影响

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