年份 |
序号 |
第一作者 |
论文题目 |
出版刊物/ 会议名称 |
分区 就高 |
2018 |
1 |
徐伟 |
Real-time reduction of tungsten impurity influx using lithium powder injection in EAST |
Fusion Engineering and Design |
2 |
2 |
潘洪涛 |
Design and implementation of 3-DOF gripper for maintenances tasks in EAST vacuum vessel |
Fusion Engineering and Design |
2 |
|
3 |
潘洪涛 |
Progress and prospects of EAST remote maintenance system |
IEEE/RSJ International Conference on Intelligent Robots and Systems (IROS) |
会议论文 |
|
4 |
谢海 |
Simulation of impurity behaviour in Experimental Advanced Superconducting Tokamak L-mode discharges with the integrated COREDIV code |
Contributions to Plasma Physics |
4 |
|
5 |
高翔 |
Sustained high βN plasmas on EAST tokamak |
Physics Letters A |
3 |
|
2019 |
1 |
仇庆来 |
Simulation of hot VDE disruption in EAST by using the TSC code |
Fusion Engineering and Design |
2 |
2 |
丁孝禹 |
TEM studies of 1 MeV Fe+ ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention |
Nuclear Fusion |
1 |
|
3 |
郝保龙 |
Modeling of the beam excited fishbone mode in EAST |
Nuclear Fusion |
1 |
|
4 |
李恭顺 |
Destabilization of field-line localized density fluctuation with a 1/1 internal kink mode in the EAST tokamak |
Nuclear Fusion |
1 |
|
5 |
李宇浩 |
Influence of hydrostatic strain on the behaviors of rhenium and osmium in tungsten |
Journal of Nuclear Materials |
1 |
|
6 |
卢棚 |
Analysis of nuclear response in CFETR toroidal field coils with density reduction VR technique |
Fusion Engineering and Design |
2 |
|
7 |
卢棚 |
Benchmark analysis of coupled neutron/decay-gamma transport method NASCA for shutdown dose rate calculation |
Fusion Engineering and Design |
2 |
|
8 |
马学斌 |
Thermal hydraulic design and analysis of updated CFETR water cooled ceramic breeder blanket |
Fusion Engineering and Design |
2 |
|
9 |
孟献才 |
Corrosion characteristics of copper in static liquid lithium under high vacuum |
Journal of Nuclear Materials |
1 |
|
10 |
王纪超 |
Effect of deuterium on bonding quality of W/Ti/Steel HIP joints in first wall application |
Fusion Engineering and Design |
2 |
|
11 |
王纪超 |
Effect of composite interlayer on bonding quality of W and steel HIP joint |
Fusion Engineering and Design |
2 |
|
12 |
吴木泉 |
Modeling and advances in the high bootstrap fraction regime on EAST towards the steady-state operation |
Nuclear Fusion |
1 |
|
13 |
谢海 |
Numerical analyses for initial-designed CFETR baseline scenario with the integrated COREDIV code |
Fusion Engineering and Design |
2 |
|
14 |
叶扬 |
Experimental study on low recycling no-ELM high confinement mode in EAST |
Nuclear Fusion |
1 |
|
15 |
张华 |
Optimization of boron nitride sphere loading in epoxy: enhanced thermal conductivity and excellent electrical insulation |
Polymers |
1 |
|
16 |
张晓龙 |
Spectral diagnostic system for light impurity transport study in J-TEXT Tokamak |
Fusion Engineering and Design |
2 |
|
17 |
张晓新 |
液态金属法制备ODS钢的研究进展 |
材料热处理学报 |
中文核心 |
|
18 |
赵文龙 |
Reliability based assessment of remote maintenance system for CFETR divertor |
Fusion Engineering and Design |
2 |
|
19 |
朱翔 |
Investigation of high harmonic fast wave for current drive on CFETR |
Fusion Engineering and Design |
2 |
|
20 |
朱秀丽 |
Reduced blister quantity in damaged tungsten exposed to deuterium plasma |
Science China Physics, Mechanics & Astronomy |
1 |
|
21 |
仇庆来 |
The numerical analysis of controllability of EAST plasma vertical position by TSC |
Fusion Engineering and Design |
2 |
|
2020 |
1 |
崔世杰 |
Three-dimensional validation and analyses of the optimized CFETR HCCB blanket |
Fusion Engineering and Design |
2 |
2 |
崔世杰 |
A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium-cooled ceramic breeder blanket |
International Journal of Energy Research |
1 |
|
3 |
崔世杰 |
Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II |
International Journal of Energy Research |
1 |
|
4 |
邓国忠 |
Simulation of divertor heat flux width on EAST by BOUT++ transport code |
Nuclear Fusion |
1 |
|
5 |
范小松 |
Microstructure and mechanical properties of similar and dissimilar joints of RAFM and 316L by electron beam welding |
Fusion Engineering and Design |
2 |
|
6 |
高翔 |
Experimental progress of hybrid operational scenario on EAST tokamak |
Nuclear Fusion |
1 |
|
7 |
龚正 |
Preliminary study and selection of CFETR in-vessel component tritium dust decontamination method in hot cell |
Fusion Engineering and Design |
2 |
|
8 |
郝保龙 |
CFETR α粒子在纵场波纹扰动下的损失模拟 |
中国科学 |
中文核心 |
|
9 |
胡朝清 |
Structure bifurcation induced by wide magnetic islands |
Nuclear Fusion |
1 |
|
10 |
胡朝清 |
Suppressive effects of diamagnetic drift on neoclassical double tearing modes based on four-field reduced MHD model |
Physics of Plasma |
3 |
|
11 |
黄天源 |
Helicon-wave-excited helium plasma performance and wall-conditioning study on EAST |
IEEE Transactions on Plasma Science |
4 |
|
12 |
黄跃恒 |
Nonlinear interactions of electrons with lower hybrid waves |
23rd Topical Conference on Radiofrequency Power in Plasmas, AIP Conference Proceedings |
会议论文 |
|
13 |
李航 |
Optimization design for plasma configuration at the CFETR |
Fusion Engineering and Design |
2 |
|
14 |
李航 |
Designing the X-divertor configurations for the China Fusion Engineering Test Reactor |
Plasma Physics and Controlled Fusion |
2 |
|
15 |
李建超 |
Reduction of sawtooth amplitude by resonant magnetic perturbation |
Nuclear Fusion |
1 |
|
16 |
刘煜锴 |
Power balance investigation in long-pulse high-performance discharges with ITER-like tungsten divertor on EAST |
Nuclear Fusion |
1 |
|
17 |
卢棚 |
Operation and shutdown dose rate analysis of CFETR ECRH system |
Fusion Engineering and Design |
2 |
|
18 |
马学斌 |
Thermo-mechanical assessment of the optimized CFETR water cooled ceramic breeder blanket |
Fusion Engineering and Design |
2 |
|
19 |
孟献才 |
Real-time gas cooling of flowing liquid lithium limiter for the EAST |
Fusion Engineering and Design |
2 |
|
20 |
潘洪涛 |
Positioning improvement based on structural and control optimization for EAST articulated maintenance arm |
Fusion Engineering and Design |
2 |
|
21 |
钱新元 |
Dynamic constitutive relationship of CuCrZr alloy based on Johnson-Cook model |
Nuclear Materials and Energy |
2 |
|
22 |
时靖谊 |
Atomic-scale mechanisms of He/V ratio effect on helium bubble hardening in iron for neutron irradiated F/M steels |
Journal of Nuclear Materials |
1 |
|
23 |
王涛 |
Dynamics of reversed shear Alfvén eigenmode and energetic particles during current ramp-up |
Nuclear Fusion |
1 |
|
24 |
谢海 |
Numerical analyses of impurity behaviors for CFETR advanced scenarios by core-edge integrated simulations |
Fusion Engineering and Design |
2 |
|
25 |
谢海 |
Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations |
Nuclear Fusion |
1 |
|
26 |
徐伟 |
Effect of lithium coating on long pulse high performance plasma discharges in EAST |
Plasma Physics and Controlled Fusion |
2 |
|
27 |
张华 |
Effect of partial substitution of Ce for La on the structural, magnetic and abnormal thermal expansion properties of La1-xCexFe11.2Al1.8 alloys |
Journal of Alloys and Compounds |
2 |
|
28 |
张逍 |
The unstable ELM evolution modulated by lower hybrid waves on EAST |
Plasma Physics and Controlled Fusion |
2 |
|
29 |
张逍 |
The factors determining the evolution of edge-localized modes in plasmas driven by lower hybrid currents |
Plasma Physics and Controlled Fusion |
2 |
|
30 |
张晓新 |
Texture evolution of tungsten materials during recrystallization |
Materials Research Express |
4 |
|
31 |
张晓新 |
Thermal shock resistance of tungsten with various deformation degrees under transient high heat flux |
Materials Research Express |
4 |
|
32 |
张晓新 |
Steam oxidation behavior of Y-bearing cladding tube with aluminizing coating |
Materials Research Express |
4 |
|
33 |
赵文龙 |
Engineering design and analysis of the CFETR divertor remote maintenance system |
IEEE Transactions on Plasma Science |
4 |
|
34 |
赵文龙 |
Strategy study and preliminary conceptual design of the remote maintenance systems for in vessel components of CFETR |
Journal of Fusion Energy |
4 |
|
35 |
朱翔 |
Observation of two threshold fields for runaway-electron generation in tokamaks |
Nuclear Fusion |
1 |
|
36 |
朱翔 |
Dependence of fishbone cycle on energetic particle intensity in EAST low-magnetic-shear plasmas |
Journal of Plasma Physics |
3 |
|
37 |
赵楠 |
Multiple Alfvén Eigenmodes Induced by Energetic-electrons and Nonlinear Mode Couplings in EAST Radio-frequency Heated H-mode Plasmas |
Nuclear Fusion |
1 |
|
38 |
刘鲁南 |
Explanation of core ion cyclotron emission from beam-ion heated plasmas in ASDEX Upgrade by the magnetoacoustic cyclotron instability |
Nuclear Fusion |
1 |