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Strategy and experimental progress of the EXL-50U spherical torus in support of the EHL-2 project

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Plasma Science and Technology 2025年第02期 39-49页

作者：石跃江宋显明郭栋姜欣辰顾翔董力立王雪韵孙恬恬谭沐芝陈正元杨光杨丹可谢华生赵寒月刘勇陶仁义李佳李松建高凡赵毅航张宇鹏张聪何宏达杨恩武杨圆明王宇宋绍栋韩磊邢博李鹏敏王振兴周培海罗文武王嵎民刘兵吴超赵鑫梁云峰董家齐袁保山彭元凯刘敏胜 the EXL-50U Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co.Ltd. Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik Southwestern Institute of physics

The EXL-50U is China's first large spherical torus device with a toroidal field reaching 1 *** major radius of the EXL-50U ranges from 0.6 m to 0.8 m,with an aspect ratio of *** goal of plasma current in the first experimental phase is 500 kA,and in the future second phase,the goal of plasma current is 1 *** the EXL-50U project,the ENN fusion team expeditiously accomplished a series of comprehensive tasks including physical and engineering design,main component construction installation,and system commissioning,all within a mere eighteen-month *** the experiments of 2024,the EXL-50U achieved a 500 kA limiter configuration discharge using ECRH(Electron Cyclotron Resonance Heating) for non-inductive current start-up and a current ramp-up with the synergetic effect of ECRH and central solenoid(CS).Preliminary divertor configuration plasmas were also obtained under 200 kA plasma *** core ion temperature of 1 keV was achieved with low-power NBI heating,and the energy confinement time of 30 ms was reached with Ohmic heating in the flat-top *** current and future experiments of EXL-50U will strongly support the physical design and operational scenarios of EHL-2 in the areas of current drive,high ion temperature exploration,energy transport and confinement,and hydrogen-boron physical *** the same time,the experience in the design,construction,and commissioning of the engineering,heating,and diagnostics systems on EXL-50U is also very beneficial for enhancing the feasibility of the engineering design for EHL-2.

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Transport analysis of the EHL-2 spherical torus in a high-ion-temperature scenario

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Plasma Science and Technology 2025年第02期 80-91页

作者：王雪韵刘文军杨丹可杨光谭沐芝姜欣辰谢华生石跃江赵寒月王嵎民梁云峰董家齐吴斌刘成岳 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik Southwestern Institute of physics Institute of Plasma physics Chinese Academy of Sciences School of physics Hefei University of Technology

EHL-2 is an ENN second-generation device aimed at studying proton-boron(p-11B) fusion reactions in a spherical *** design parameters are Ti0～30 keV,Ti/Te>2,ne0～1×1020m-3,Ip～3 MA,B_t～3 T,and τE～0.5 *** ion temperature is one of the standard operation scenarios of EHL-2,aiming to reduce bremsstrahlung radiation while enhancing plasma parameters by elevating the ion to electron temperature *** order to achieve high ion temperature,neutral beam injection is considered the primary heating method during the flat-top *** neutral beam system for EHL-2 comprises 3-5 beams with energy/power ranging from 60 keV/4 MW,80-100 keV/10 MW,to 200 keV/3 *** work conducts predictive analysis on core transport during the flat-top phase of EHL-2's high-ion-temperature scenario utilizing *** study delineates the potential operating range of core temperature and other parameters given the designed heating ***,the study presents predictive simulations based on CDBM,GLF23,Bohm-gyro-Bohm,and IFSPPPL transport models,evaluating the steady-state power balance,energy confinement time,and impact of various parameters such as plasma density and NBI power on core ion *** simulations demonstrate that the design parameters of the EHL-2 high-Tiscenario,although sensitive to varying transport models,are hopefully attainable as long as adequate ion heating and controlled ion transport levels are ensured.

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Poloidal field system and advanced divertor equilibrium configuration design of the EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 125-133页

作者：顾翔尹刚石跃江董力立王宇臧红杨圆明谢华生董家齐彭元凯袁保山杨青巍梁云峰宋显明刘敏胜 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. Southwestern Institute of physics Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik

The EHL-2（ENN He-Long 2） spherical torus（ST） project focuses on advancing spherical torus technology to address the unique challenges of p-11B fusion,which demands significantly higher ion temperature and heat flux to the divertor plate compared to traditional deuterium-tritium *** a major radius of 1.05 m and a plasma current of 3 MA,the project aims to evaluate and optimize advanced divertor configurations,specifically the Super-X and X-point target（XPT）*** design incorporates an up-down double-null configuration featuring a conventional inner divertor and an XPT outer divertor to effectively reduce the heat *** poloidal field（PF） coil system is meticulously optimized to balance engineering constraints with the flexibility in equilibrium *** design is expected to provide a reference equilibrium configuration for other physics design issues and offer critical insight into heat load management.

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Predictions of gyrokinetic turbulent transport in proton-boron plasmas on EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 92-101页

作者：谭沐芝许健强杜华荣董家齐谢华生王雪韵黄贤礼王嵎民顾翔刘兵石跃江梁云峰 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. Southwestern Institute of physics Southwest Jiaotong University Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasma Physics Partner of the Trilateral Euregio Cluster (TEC)

The EHL-2 spherical torus at ENN is the next-generation experimental platform under conceptual design,aiming at realizing proton-boron(p-11B) thermonuclear fusion,which is an attractive pathway towards neutron-free *** achieve high-performance steady-state plasma,it is extremely necessary to study the turbulence transport characteristics with high boron content in the plasma *** study investigates the transport properties in the core internal transport barrier（ITB） region of p-11B plasma utilizing the gyrokinetic code GENE in view of the high ion temperature scenario of EHL-2,specifically focusing on the impact of boron fractions and plasma β on the microinstabilities and corresponding transport *** findings indicate that the inclusion of boron species effectively suppresses the trapped electron modes（TEMs） as well as promoting a transition from electromagnetic to electrostatic turbulence with increased boron fraction,which is a result of the suppression of microinstabilities by effective charge and ***,it has been identified that the external E×B rotational shear has a notable inhibitory influence on transport,which can reduce the transport level by two to three orders of magnitude,especially at medium boron *** suppressive effect of E×B on turbulence is weakened once the kinetic ballooning mode（KBM） is excited and the transport shows a rapid increase with β together with a reduction in zonal flow amplitude,which is consistent with previous ***,it is strongly suggested that exploring advanced strategies for mitigating turbulent transport at high β regimes is necessary for the active control of plasma behavior regarding p-11B plasma-based fusion devices such as EHL-2.

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Evaluation of thermal and beam-thermal p-11B fusion reactions in the EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 50-58页

作者：李直孙恬恬刘兵王丰吴相凤彭元凯肖骁赵冠超马连良李颖颖林展宏孔浩喆梁云峰谢华生董家齐石跃江罗迪姜欣辰王嵎民顾翔王雪韵谭沐芝黄海荣杨丹可蔡剑青董力立王泉云刘敏胜 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. Shandong University Dalian University of Technology Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik Southwestern Institute of physics

This paper presents the first comprehensive simulation study of p-11B fusion reactions in a spherical *** developed relevant program modules for fusion reactions based on energetic particle simulation frameworks and analyzed the two main fusion channels:thermal and *** EHL-2 design parameters with nboron=0.07nionand a hydrogen beam at 200 keV and 1 MW,our simulation indicates that p-11B reactions produce approximately 1.5×1015αparticles per second（～0.7 kW） from the thermal channel,and 5.3 × 1014（～0.25 kW） from the beam-thermal *** conducted parameter scans to establish a solid physics foundation for the high ion temperature conditions（Ti> 26 keV） designed for *** work also laid the groundwork for studying various operation modes to explore different reaction *** simulation results suggest that the conditions in EHL-2 could be sufficient for investigating p-11B thermonuclear *** addition,we found that EHL-2 offered good confinement for energetic particles,allowing us to research the interactions between these ions and *** research enhances our understanding of burning plasma physics.

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Instabilities of ideal magnetohydrodynamics mode and neoclassical tearing mode stabilization by electron cyclotron current drive for EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 69-79页

作者：董力立李莉刘文军刘桐梁云峰董家齐谢华生石跃江 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. College of Science Donghua University Key Laboratory of Materials Modification by Laser Ion and Electron Beams (Ministry of Education)School of Physics Dalian University of Technology Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasma Physics Partner of the Trilateral Euregio Cluster (TEC) Southwestern Institute of physics

The next generation fusion device listed on ENN's fusion roadmap,named as(ENN He-Long)EHL-2,is under both physics and engineering *** instabilities of ideal magnetohydrodynamics(MHD) mode and neoclassical tearing mode(NTM) stabilized by electron cyclotron current drive(ECCD) for EHL-2's two typical operation scenarios are *** high-ion-temperature operating(HITO) scenario,the vertical displacement event(VDE)could be a big challenge to the device *** the steady-state operating(SSO) scenario,the limitation may rise from the ideal MHD mode,NTM,*** suggests that the MHD analysis of both operation scenarios should be done with different *** analysis based on the current physics and engineering design of both two scenarios is given in this *** on the analysis result of above,the future assessments might target at active control method and the effect of boron on MHD activities.

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Divertor heat flux challenge and mitigation in the EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 102-114页

作者：王福琼顾翔华建坤王嵎民薄晓坤陈博石跃江徐帅王二辉梁云峰 the EHL-2 Team College of physics Donghua University Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma physics State Key Laboratory of Advanced Electromagnetic Engineering and Technology School of Electrical and Electronic Engineering Huazhong University of Science and Technology Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasma Physics

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） *** paper presents the design of an X-point target（XPT） divertor,featuring a conventional inner divertor and an XPT outer divertor,aimed at the effective control of heat loads,which may be extremely high during high ion temperature *** divertor target plates are made from carbon-based materials,which can handle heat loads of up to 5 MW/*** performances,including the heat load controllability,the onset of detachment and the in-out/up-down asymmetry,etc.,are evaluated using both the simple particle-tracking strategy and the complicated SOLPS-ITER *** attention is paid to the drift effects on particle/heat transport in the divertor/scrape-off layer region and on the divertor heat loads,focusing on the semi-detached/detached operation *** from SOLPS-ITER simulations demonstrated that the currently designed magnetic equilibrium and divertor configuration can effectively handle the power heat load in EHL-2.

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Disruption prediction and mitigation strategies in the EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 148-157页

作者：蔡剑青梁云峰陈忠勇郑玮胡地薛雷林志芳顾翔 the EHL-2 Team Hebei Key Laboratory of Compact Fusion Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma physics School of Electrical and Electronic Engineering Huazhong University of Science and Technology School of physics Beihang University Southwestern Institute of physics School of Electrical Engineering & Automation Jiangsu Normal University ENN Science and Technology Development Co. Ltd.

EHL-2 is a compact,high-field spherical tokamak designed to explore the potential of an advanced p-11B nuclear fusion *** to its high plasma current and thermal energy,it is crucial to mitigate the impact associated with disruptions to ensure the safe operation of *** paper evaluates the performance requirements of the disruption prediction system on EHL-2,with a particular focus on applying generalizable knowledge transfer from existing devices to future ***,the key characteristics of disruption mitigation strategies are analyzed,and their overall mitigation performance on EHL-2 is *** insight provides valuable guidance for optimizing the engineering design of EHL-2 and identifying its optimal operational regime.

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Predictions of H-mode access and edge pedestal instability in the EHL-2 spherical torus

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Plasma Science and Technology 2025年第02期 59-68页

作者：王嵎民李凯黄卓刘一良戴舒宇张洁黄艳清顾翔赵毅航徐帅王二辉郭栋石跃江谢华生梁云峰刘敏胜 the EHL-2 Team Hebei Key Laboratory of Compact Fusion ENN Science and Technology Development Co. Ltd. Centre for Theoretical and Computational physics College of Physics Qingdao University College of Computer Science South-Central Minzu University Key Laboratory of Materials Modification by Laser Ion and Electron Beams (Ministry of Education)School of Physics Dalian University of Technology Department of Plasma physics and Fusion Engineering University of Science and Technology of China College of physics and Electronic Engineering Hengyang Normal University Forschungszentrum Jülich GmbH Institute of Fusion Energy and Nuclear Waste Management-Plasmaphysik

The EHL-2 spherical torus is designed to demonstrate proton-boron(p-11B) fusion within a compact spherical *** planned heating system includes a negative ion-based neutral beam injection（N-NBI）,two positive ion-based NBI systems（P-NBI）,electron cyclotron resonance heating（ECRH）,ion cyclotron resonance heating（ICRH）,and high harmonic fast wave（HHFW）,with a total power output of 31 *** to scaling law estimates,the device is capable of achieving H-mode *** plasma density,ne,min,at the minimum LH power threshold,PLH,is estimated to be 4.4× *** pedestal parameters were calculated using the REPED *** B as the primary impurity ion,the predicted pedestal width and height are lower compared to the typical case with carbon *** pedestal collisionality for EHL-2 is estimated to range between 0.06 and 0.17,indicating the potential for significant energy loss due to edge localized modes（ELMs）.The heat flux on the divertor plate has been calculated using the JOREK *** peak heat fluxes during ELM bursts are approximately 31.0 MW/m2at the lower inboard target and 39.5 MW/m2at the lower outboard target.A preliminary design of the resonant magnetic perturbation（RMP） coils has been completed to both control type-Ⅰ ELMs and correct error *** system comprises 16coils arranged into 2×4 *** ELM control mode,a 14/2 component is generated at 1.7 G/kAt,with a current of 4.9 kA required to achieve σChirikov=1 at the resonant surface,where the normalized poloidal magnetic flux is *** error field（EF） modulation mode,2/1 and 3/1components are generated at 3.5 G/kAt and 2.8 G/kAt,respectively.

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