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DIVERTOR: 作品数：121被引量：45H指数：4; 导出分析报告; 相关领域：核科学技术理学更多>>; 相关作者：赵伟钟光武更多>>; 相关机构：中国核工业集团公司中国科学技术大学更多>>; 相关期刊：《Southwestern Institute of Physics Annual Report》《Natural Science》《Science China(Technological Sciences)》《Journal of Thermal Science》更多>>; 相关基金：国家自然科学基金中国博士后科学基金国家重点基础研究发展计划更多>>

Divertor heat flux challenge and mitigation in the EHL-2 spherical torus: 《Plasma Science and Technology》2025年第2期97-109,共13页Fuqiong WANG Xiang GU Jiankun HUA Yumin WANG Xiaokun BO Bo CHEN Yuejiang SHI Shuai XU Erhui WANG Yunfeng LIANG the EHL-2 Team; sponsored by the Fundamental Research Funds for the Central Universities(No.232024G-10)and National Natural Sciences Foundation of China(Nos.12075052,12275098 and 12275307);the ENN Group and the ENN Energy Research Institute.; The divertor design is critical to heat load handling and thus to achievements of highperformance plasma operations in the EHL-2(ENN He-Long 2)tokamak.This paper presents the design of an X-point target(XPT)divertor,f...; 关键词：heat flux DIVERTOR EHL-2

Poloidal field system and advanced divertor equilibrium configuration design of the EHL-2 spherical torus: 《Plasma Science and Technology》2025年第2期120-128,共9页Xiang GU Gang YIN Yuejiang SHI Lili DONG Yu WANG Hong ZANG Yuanming YANG Huasheng XIE Jiaqi DONG Yueng-Kay Martin PENG Baoshan YUAN Qingwei YANG Yunfeng LIANG Xianming SONG Minsheng LIU the EHL-2 Team; supported by the ENN Group and the ENN Energy Research Institute.; The EHL-2(ENN He-Long 2)spherical torus(ST)project focuses on advancing spherical torus technology to address the unique challenges of p-^(11)B fusion,which demands significantly higher ion temperature and heat flux t...; 关键词：PF system EQUILIBRIUM X-point target divertor

Estimates of required impurity fraction for EAST divertor detachment: 《Plasma Science and Technology》2025年第1期30-38,共9页Jing OU Jiamin LONG; supported by National Natural Science Foundation of China(No.12375227);Innovation in Fusion Engineering Technology of Institute(No.E35QT1080C)。; During the EAST radiative divertor experiments,one of the key challenges was how to avoid the occurrence of disruptive events caused by excessive impurity seeding.To estimate the required impurity fraction for diverto...; 关键词：divertor detachment IMPURITY radiative divertor reduced physics model

Characteristics of divertor heat flux distribution with an island divertor configuration on the J-TEXT tokamak: 《Plasma Science and Technology》2024年第12期9-17,共9页Yutong YANG Yunfeng LIANG Wei YAN Shuangbao SHU Jiankun HUA Song ZHOU Qinghu YANG Jinlong GUO Ziyang JIN Wei XIE the J-TEXT Team; supported by the National Magnetic Confinement Fusion Energy R&D Program of China(No.2018YFE0309103);National Natural Science Foundation of China(Nos.12305243 and 51821005)。; On J-TEXT,the temporal evolution of heat flux distribution on the high-field side(HFS)divertor plate has been measured by an infrared(IR)camera during the plasma operation with an island divertor configuration.In expe...; 关键词：infrared camera island divertor heat flux SMBI power detachment

Comparative study of boron and neon injections on divertor heat fluxes using SOLPS-ITER simulations: 《Chinese Physics B》2024年第11期312-321,共10页Lei Peng Zhen Sun Ji-Zhong Sun Rajesh Maingi Fang Gao Xavier Bonnin Hua-Yi Chang Wei-Kang Wang Jin-Yuan Liu; Project supported by the National Key R&D Program of China(Grant No.2019YFE03030004);the National Natural Science Foundation of China(Grant No.12275040);the Users with Excellence Program of Hefei Science Center CAS(Grant No.2020HSC-UE010);This research is also sponsored in part by the U.S.Department of Energy under contract DEAC02-09CH11466.; Based on the EAST equilibrium,the effects of boron(B)and neon(Ne)injected at different locations on the target heat load,and the distributions of B and Ne particles were investigated by transport code SOLPS-ITER.It wa...; 关键词：BORON NEON injection location heat flux

Simulation of tungsten impurity transport by DIVIMP under different divertor magnetic configurations on HL-3: 《Plasma Science and Technology》2024年第10期29-38,共10页Qingrui ZHOU Yanjie ZHANG Chaofeng SANG Jiaxian LI Guoyao ZHENG Yilin WANG Yihan WU Dezhen WANG; supported by National Natural Science Foundation of China(Nos.12235002 and 12122503);National Key R&D Program of China(No.2018YFE0301101);Dalian Science&Technology Talents Program(No.2022RJ11);Xingliao Talent Project(No.XLYC2203182)。; Tungsten(W)accumulation in the core,depending on W generation and transport in the edge region,is a severe issue in fusion reactors.Compared to standard divertors(SDs),snowflake divertors(SFDs)can effectively suppress...; 关键词：snowflake divertor neon seeding tungsten transport DIVIMP HL-3

Design of a 3D-printed liquid lithium divertor target plate and its interaction with high-density plasma: 《Plasma Science and Technology》2024年第8期112-120,共9页苑聪聪叶宗标刘建星郭恒鑫彭怡超廖加术陈波陈建军王宏彬韦建军张秀杰芶富均; funded by the China Postdoctoral Science Foundation(No.2019M663487);the National Key Research and Development Program of China(No.2022YFE03130000)。; A liquid Li divertor is a promising alternative for future fusion devices.In this work a new divertor model is proposed,which is processed by 3D-printing technology to accurately control the size of the internal capil...; 关键词：fusion DIVERTOR 3D-printing TUNGSTEN LITHIUM liquid metal

Calculation and prediction of divertor detachment via impurity seeding by using one-dimensional model: 《Chinese Physics B》2024年第8期370-379,共10页周文杰刘晓菊邬潇河李邦石奇奇樊皓尘杨艳杰李国强; Project supported by the National Key Research and Development Program of China (Grant No.2022YFE03030001);the National Natural Science Foundation of China (Grant No.12075283)。; Achieving the detachment of divertor can help to alleviate excessive heat load and sputtering problems on the target plates,thereby extending the lifetime of divertor components for fusion devices.In order to provide ...; 关键词：divertor detachment impurity seeding one-dimensional modeling

SOLPS-ITER drift modeling of neon impurity seeded plasmas in EAST with favorable and unfavorable toroidal magnetic field direction: 《Plasma Science and Technology》2023年第11期66-83,共18页王福琼梁云峰徐颖峰查学军钟方川毛松涛段艳敏胡立群; supported by National Natural Sciences Foundation of China(Nos.12075052,12175034 and 12275098);National Key R&D Program of China(Nos.2018YFE0309103,2017YFE0301100 and 2017YFE0301104)。; To better understand divertor detachment and asymmetry in the Experimental Advanced Superconducting Tokamak(EAST),drift modeling via the comprehensive edge plasma code SOLPS-ITER of neon impurity seeded plasmas in fav...; 关键词：DRIFTS electric potential/field asymmetry divertor detachment impurity transport

Closed corner divertor with B×▽B away from the divertor:a promising divertor scenario for tokamak power exhaust: 《Plasma Science and Technology》2023年第10期60-67,共8页徐国盛贾国章丁根凡陶余强孟令义余林王亮刘建斌; funded by the National Magnetic Confinement Fusion Program of China(Nos.2019YFE03030000,2019YFE03080500 and 2022YFE03060004);National Natural Science Foundation of China(No.U19A20113)。; A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared with present experience...; 关键词：divertor concept closed divertor corner E×B drifts SOLPS-ITER simulation EAST tokamak

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