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
{"title":"MHD Analysis on the Physics Design of CFETR Baseline Scenarios","authors":"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","doi":"10.1007/s10894-022-00323-x","DOIUrl":null,"url":null,"abstract":"<div><p>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.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2022-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-022-00323-x","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 2
Abstract
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.
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.