CFETR基线情景物理设计的MHD分析

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Journal of Fusion Energy Pub Date : 2022-06-01 DOI:10.1007/s10894-022-00323-x
Ping Zhu, Li Li, Yu Fang, Yuling He, Shuo Wang, Rui Han, Yue Liu, Xiaojing Wang, Yang Zhang, Xiaodong Zhang, Qingquan Yu, Liqun Hu, Huihui Wang, Youwen Sun, Lai Wei, Weikang Tang, Tong Liu, Zhengxiong Wang, Xingting Yan, Wenlong Huang, Yawei Hou, Xiaoquan Ji, Shiyong Zeng, Zafar Abdullah, Zhongyong Chen, Long Zeng, Haolong Li, Zhipeng Chen, Zhijiang Wang, Bo Rao, Ming Zhang, Yonghua Ding, Yuan Pan, the CFETR Physics Team
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引用次数: 2

摘要

中国聚变工程试验堆(CFETR)是目前中国正在进行密集的物理和工程设计的一个重大项目,代表了低密度稳态途径的受控聚变能。CFETR物理设计的主要任务之一是评估和分析所提出的设计方案的磁流体动力稳定性。对CFETR基线情景的综合MHD稳定性评估已经取得了初步进展,这可能进一步有利于工程设计。对于CFETR,本文预测了新经典撕裂模式(NTM)完全稳定所需的电子回旋电流驱动(ECCD)功率和电流,以及相应的可控磁岛宽度。对CFETR的电阻壁模稳定性进行了深入的研究。对于80%的稳态运行场景,可能需要主动控制方法来稳定RWM。模拟了CFETR上大量氖注入的干扰缓解过程。估计了等离子体在CFETR上破坏的时间尺度和后果,发现CFETR相当于国际热核实验反应堆(ITER)。主要的MHD不稳定性,如NTM和RWM,仍然是稳态托卡马克运行的挑战。在此基础上,CFETR MHD研究的下一步计划是NTM, RWM和破碎颗粒注射(SPI)中断缓解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

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MHD Analysis on the Physics Design of CFETR Baseline Scenarios

The China Fusion Engineering Test Reactor (CFETR), currently under intensive physics and engineering designs in China, is a major project representative of the low-density steady-state pathway to the controlled fusion energy. One of the primary tasks of the physics design for CFETR is the assessment and analysis of the magnetohydrodynamic (MHD) stability of the proposed design schemes. Comprehensive MHD stability assessment of the CFETR baseline scenarios have led to preliminary progress that may further benefit engineering designs. For CFETR, the electron cyclotron current drive (ECCD) power and current required for the full stabilization of neoclassical tearing mode (NTM) have been predicted in this work, as well as the corresponding controlled magnetic island width. A thorough investigation on resistive wall mode (RWM) stability for CFETR is performed. For 80% of the steady state operation scenarios, active control methods may be required for RWM stabilization. The process of disruption mitigation with massive neon injection on CFETR is simulated. The time scale of and consequences of plasma disruption on CFETR are estimated, which are found equivalent to International Thermonuclear Experimental Reactor (ITER). Major MHD instabilities such as NTM and RWM remain challenge to steady state tokamak operation. On this basis, next steps on CFETR MHD study are planned on NTM, RWM, and shattered pellet injection (SPI) disruption mitigation.

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来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
期刊介绍: The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.
期刊最新文献
Research on Insulation Technology for Nb3Sn Layer Coil of Superconducting Conductor Testing Facility Preliminary Control-Oriented Modeling of the ITER Steering Mirror Assembly and Local Control System in the Electron Cyclotron Heating & Current Drive Actuator High Energy Density Radiative Transfer in the Diffusion Regime with Fourier Neural Operators Retraction Note: Determination of the Plasma Internal Inductance and Evaluation of its Effects on Plasma Horizontal Displacement in IR-T1 Tokamak Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak
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