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The Innovation 2024年第1期5卷 23-25页

作者： Guosheng Xu Zhiyuan Lu Dehong Chen baonian wan Institute of Plasma Physics Chinese Academy of SciencesHefei 230031China

The stellarator has inherent advantages over the tokamak in achieving steady-state operation,especially due to its absence of disruptions and lack of need for current drive and the associated recirculating power.In recent years,there have been remarkable advances in the field of stellarator optimization,where precisely quasi-symmetric and precisely quasi-isodynamic magnetic configurations have been achieved with coils,allowing the neoclassical transport and energetic particle losses of stellarators to be reduced to levels comparable to those of tokamaks.At the same time,the development of high-temperature superconducting magnet technology will potentially double the magnetic field strength of stellarators.While these strong fields are expected to introduce new challenges,and while turbulent transport remains a common challenge for both stellarators and tokamaks,the combination of these physical and technological advances results in the expectation that stellarators will become a competitive approach to tokamaks for realizing steady-state fusion.

关键词： field approach precise

Edge localized modes suppression via edge E × B velocity shear induced by RF sheath of ion cyclotron resonance heating in EAST

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Science China(Physics,Mechanics & Astronomy) 2022年第3期65卷 71-76页

作者： XinJun Zhang Chu Zhou XiaoLan Zou TianYang Xia YanLong Li ChengMing Qin XianZu Gong Qing Zang MingHui Li Tao Zhang ShouXin wang HaiQing Liu Guillaume Urbanczyk Adi Liu YanMing Duan YanPing Zhao JinPing Qian Robert Isaac Pinsker MinYou Ye baonian wan Institute of Plasma Physics Chinese Academy of Sciences(ASIPP)Hefei 230031China School of Nuclear Sciences and Technology University of Science and Technology of ChinaHefei 230026China CEA IRFMSaint-Paul-les-Durance F-13108France Key Laboratory of Optoelectronic Devices and Systems College of Physics and Optoelectronic EngineeringShenzhen UniversityShenzhen 518060China General Atomics San Diego CA 92186-5608USA

The control of large edge localized modes(ELMs) is a critical issue for the successful operation of future burning plasma devices,such as the international thermonuclear experimental reactor(ITER) and China fusion engineering test reactor(CFETR). In this paper, we present a new active and effective means of ELM suppression using ion cyclotron resonant heating(ICRH) on the experimental advanced superconducting tokamak(EAST). We obtained the key role of the external E × B velocity shear near the pedestal top and the scrape-off-layer(SOL) induced by the RF sheath potential of ICRH in ELM suppression. The experimental results showed a positive correlation between the RF sheath and the E × B shear rate in SOL. BOUT++ simulations indicate that increased E × B velocity shear rates in the pedestal and SOL regions promote ELM suppression;thereby, supporting the experimental observations on EAST. These findings suggest a new simple approach to access the ELM suppressed regimes in plasma with low torque input as ITER baseline discharges.

关键词： ion cyclotron resonant heating RF sheath edge localized mode suppression E×B velocity shear

Steady-state burning plasma: a new stage in the development of magnetic confinement fusion energy

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National Science Review 2023年第12期10卷 58-60页

作者：万宝年徐国盛 Institute of Plasma Physics Chinese Academy of Sciences

In the last century, the fusion triple product n TτE (density, ion temperature and energy confinement time) obtained on tokamak devices have increased faster than the ‘Moore’s law’ in the field of chips.However, after the JET, TFTR and JT-60 U three large devices, the international joint construction of the International Thermonuclear Experimental Reactor(ITER) began. No larger device has been built yet,

关键词： DT fusion Steady-state burning plasma high-temperature superconductor magnetic confinement fusion strong magnetic field tokamak

A New Path to Improve High β_p Plasma Performance on EAST for Steady-State Tokamak Fusion Reactor

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Chinese Physics Letters 2020年第4期37卷 85-87页

作者：万宝年无 Institute of Plasma Physics Chinese Academy of SciencesHefei 230031 the EAST team

High βp scenario is foreseen to be a promising candidate operational mode for steady-state tokamak fusion reactors.Dedicated experiments on EAST and data analysis find that density gradient ▽n is a control knob to improve energy confinement in high βp plasmas at low toroidal rotatoon as projected for a fusion reactor.Different from previously known turbulent stabilization mechanisms such as E × B shear and Shafranov shift,high density gradient can enhance the Shafranov shift stabilizing effect significantly in high βp regime,giving that a higher density gradient is readily accessible in future fusion reactors with lower collisionality.This new finding is of great importance for the next-step fusion development because it may open a new path towards even higher energy conBnement in the high βp scenario.It has been demonstrated in the recent EAST experiments,i.e.,a fully non-inductive high βp(~2) H-mode plasma(H98y2≥1.3) has been obtained for a duration over 100 current diffusion times,which sets another new world record of long-pulse high-performance tokamak plasma operation with the normalized performance approaching the ITER and CFETR regimes.

关键词： mode Plasma approaching

Spectroscopic Measurements of Impurity Spectra on the EAST Tokamak

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Plasma Science and Technology 2012年第12期14卷 1048-1053页

作者： FU Jia LI Yingying SHI Yuejiang wanG Fudi ZHANG Wei LV Bo HUANG Juan wan baonian ZHOU Qian Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031 China University of Science and Technology of China Hefei 230039 China WCI Center for Fusion Theory National Fusion Research Institute 52 Eoeun-Dong Yusung-Gu Daejeon 305-333 South Korea School of Natural Sciences Anhui Agricultural University Hefei 230036 China

Ultraviolet （UV） and visible impurity spectra （200-750 nm） are commonly used to study plasma and wall interactions in magnetic fusion plasmas. Two optical multi-channel analysis （OMA） systems have been installed for the UV-visible spectrum measurement on EAST. These two OMA systems are both equipped with the Czerny-Turner （C-T） type spectrometer. The upper vacuum vessel and inner divertor baffle can be viewed simultaneously through two optical lenses. The OMA1 system is mainly used for multi-impurity lines radiation measurement. A 280 nm wavelength range can be covered by a 300 mm focal length spectrometer equipped with a 300 grooves/mm grating. The Da/Ha line shapes can be resolved by the OMA2 system. The focal length is 750 mm. The spectral resolution can be up to 0.01 nm using a 1800 grooves/mm grating. The impurity behaviour and hydrogen ratio evolution after boroniztion, lithium coating, and siliconization are compared. Lithium coating has shown beneficial effects on the reduction of edge recycling and low Z impurity （C, O） influx. The impurity expelling effect of the divertor configuration is also briefly discussed through multi-channels observation of OMA1 system.

关键词： OMA optical multi channel analysis boronization lithium coating wall condition tokamak

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我国磁约束聚变研究进展和展望

中国科学基金 2008年第1期22卷 1-7页

作者：万宝年中国科学院等离子体物理研究所合肥230031

我国磁约束聚变近年来在工程技术发展和物理研究方面都取得了一些重要进展,一些研究已与未来聚变反应堆所涉及的重大前沿课题密切相关。随着HL-2A装置的不断完善和国际上第一个非圆截面全超导托卡马克EAST的投入运行,以及中国加入国际... 详细信息

我国磁约束聚变近年来在工程技术发展和物理研究方面都取得了一些重要进展,一些研究已与未来聚变反应堆所涉及的重大前沿课题密切相关。随着HL-2A装置的不断完善和国际上第一个非圆截面全超导托卡马克EAST的投入运行,以及中国加入国际热核实验反应堆计划,为中国聚变事业带来了前所未有的发展机遇。

关键词：磁约束聚变等离子体

Development of Neutron Emission Spectrometers for Tokamak Plasma Diagnostics

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Development of Neutron Emission Spectrometers for Tokamak Pl...

第十六届全国等离子体科学技术会议暨第一届全国等离子体医...

作者： Tieshuan FAN Xi YUAN Xing ZHANG Xufei XIE Zhongjing CHEN Xingyu PENG Lin HUAN Tao LI Jinxiang CHEN Xiangqing LI Guohui ZHANG Guoqiang ZHONG Liqun HU Shiyao LIN baonian wan Guoliang YUAN Yipo ZHANG Jinwei YANG Qingwei YANG Institute of Heavy Ion Physics school of PhysicsPeking University Institute of Plasma Physics CAS SouthWestern Institute of Physics

Digital 2.5 MeV fusion neutron spectrometers,based on liquid scintillators and stilbene crystal detectors,have been developed in HL-2A and EAST tokamaks.New digital pulse shape discrimination techniques,including the digital delay-line-shape(DDLS) method and moment analysis(MA),are presented and a count rate of about 45 kHz has

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光谱法研究等离子体粒子循环和输运

光学学报 2005年第4期25卷 557-560页

作者：徐伟梁铨廷万宝年广州大学物理系广州510405 中国科学院等离子体物理研究所合肥230031

介绍了三高斯拟合技术,首先用单高斯选点拟合了Hα线形分布的远翼,由谱线的多谱勒展宽得出等离子体离子温度为170 eV,再对剩余量进行双高斯拟合,从多谱勒频移求出反射和解吸粒子入射速度分别为3.0×104 m/s和1×104 m/s,从谱线辐射强度... 详细信息

介绍了三高斯拟合技术,首先用单高斯选点拟合了Hα线形分布的远翼,由谱线的多谱勒展宽得出等离子体离子温度为170 eV,再对剩余量进行双高斯拟合,从多谱勒频移求出反射和解吸粒子入射速度分别为3.0×104 m/s和1×104 m/s,从谱线辐射强度推出再循环粒子由60%反射粒子和40%解吸粒子组成.在简化模型下讨论了粒子的输运行为,算出了氢原子密度、体发射系数和粒子约束时间的分布,均与实验结果相符.分析了粒子入射速度大小对粒子约束时间的影响,结果表明,正常放电下,HT-6M托卡马克粒子约束时间在4～8 ms反射粒子的速度大小直接决定粒子约束时间的大小和空间分布.

关键词：光谱学等离子体高斯拟合粒子循环粒子输运

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EAST超导托卡马克

科学通报 2015年第23期60卷 2157-2168页

作者：万宝年徐国盛中国科学院合肥物质科学研究院等离子体物理研究所合肥230031

EAST超导托卡马克是我国设计建造的国际上第一个建成的全超导托卡马克实验装置.EAST的建成填补了从短脉冲中型常规托卡马克向长脉冲大型超导托卡马克过渡过程中"中型超导托卡马克"的空缺.EAST具有国际热核聚变实验堆(ITER)类似先进技术... 详细信息

EAST超导托卡马克是我国设计建造的国际上第一个建成的全超导托卡马克实验装置.EAST的建成填补了从短脉冲中型常规托卡马克向长脉冲大型超导托卡马克过渡过程中"中型超导托卡马克"的空缺.EAST具有国际热核聚变实验堆(ITER)类似先进技术,具有与ITER类似的超过1000 s的长脉冲高参数运行能力,是未来10年国际上极少数有能力在高参数条件下开展长脉冲聚变等离子体物理和工程技术研究的实验平台.EAST已经取得了超过400 s的偏滤器位形等离子体以及稳定重复的超过30 s的长脉冲"高约束模"等离子体,创造了新纪录.EAST致力于解决ITER及未来聚变堆高性能稳态运行相关的关键物理和工程问题.这些研究将为中国未来聚变实验堆的设计和运行提供重要的依据,并为未来建造稳态、高效、安全的托卡马克类型的聚变反应堆提供重要的工程技术和物理基础.

关键词：超导托卡马克磁约束聚变受控核聚变国际热核聚变实验堆

HT-7积分器系统的定时触发模块设计与实现

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核技术 2009年第4期32卷 309-312页

作者：刘冬梅万宝年沈飚中国科学院等离子体物理研究所合肥230031

本文设计一种积分器系统中的定时触发模块,详细介绍用单片机和晶体管设计定时触发模块的设计思路、硬件结构和软件设计等方面的内容。该模块为积分器系统提供精确的可调积分定时时间,且触发准确、驱动能力强。定时触发模块提高了积分器... 详细信息

本文设计一种积分器系统中的定时触发模块,详细介绍用单片机和晶体管设计定时触发模块的设计思路、硬件结构和软件设计等方面的内容。该模块为积分器系统提供精确的可调积分定时时间,且触发准确、驱动能力强。定时触发模块提高了积分器系统的可靠性和适用范围,满足HT-7实验要求。

关键词：定时触发模件单片机积分器 HT-7