DIVERTOR相关论文
This paper presents the nuclear analysis performance of the Chinese Fusion Engineering Test Reactor(CFETR)divertor regio......
Numerical simulation of plasma facing component with Built-in tungsten filament on basis of join W/C
A novel model with built-in tungsten filament on the basis of join W/Cu functionally graded layer was proposal and inves......
Research on characteristics of helium plasma and irradiation damage to tungsten surface in cascade a
In fusion reactor,the divertor is used to filter the helium ash produced in the reaction.Tungsten is a plausible candida......
HL-2M is a new medium-sized copper-conductor tokamak device under construction at Southwestern Institute of Physics and ......
Silicon carbide(SiC)is an expectant candidate of structural materials for fusion reactors after Demonstration Power Plan......
This paper generally compares the essential features between tokamaks and stellarators, based on previous review work in......
为旋涡水流计算的一个有效方法被使用 ANSYS 为东方新 divertor 开发了。为 EAST 设备的双空 divertor 的 A 3D 模型被造评估旋涡......
在托卡马克偏滤器区域充入杂质气体是检验偏滤器杂质屏蔽效应的重要手段。利用快速极紫外EUV光谱仪对EAST托克马克装置上开展的偏......
本文通过对荣华二采区10...
本文通过对荣华二采区10...
Achieving temporary divertor plasma detachment with MARFE events by pellet injection in the EAST sup
本文通过对荣华二采区10...
本文通过对荣华二采区10...
OEDGE modeling of plasma contamination efficiency of Ar puffing from different divertor locations in
本文通过对荣华二采区10...
为探究吕家坨井田地质构造格局,根据钻孔勘探资料,采用分形理论和趋势面分析方法,研究了井田7......
为探究吕家坨井田地质构造格局,根据钻孔勘探资料,采用分形理论和趋势面分析方法,研究了井田7......
为探究吕家坨井田地质构造格局,根据钻孔勘探资料,采用分形理论和趋势面分析方法,研究了井田7......
Tungsten is a promising candidate for plasma-facing materials to cover the surface of the divertor plate in the design o......
The outer divertor plasma of HL-2A and its associated scrape-off plasma have been simulated using a two-dimensional mult......
Impurity is one of the key issues on a great impact to the quality of tokamak plasma.HL-2A is the first divertor tokamak......
Tungsten is a promising candidate for plasma-facing materials to cover the surface of the divertor plate in the design o......
During the discharging of Tokamak devices, interactions between the core plasma and plasma-facing components (PFCs) may ......
基于中国聚变工程试验堆(CFETR)偏滤器位形,初步设计了指状、平板和T形三种氦冷偏滤器模型,在10MPa入口氦压力、10MW·m^(-2)......
使用热侵蚀沉积粒子程序(HEDPIC)模拟了由小块沿环向表面倾斜的瓦片组成类ITER偏滤器的极向缝隙附近瓦片表面的热流密度分布,研究......
偏滤器是现代磁约束核聚变堆试验装置中一个非常重要的部件,其中面向等离子体材料、热沉材料和结构材料之间物理性能差异大的异种材......
总结了作为PFCs中最重要部分的偏滤器(Divertor)在制备过程中控制部件复合界面质量的超声检测和红外热像技术。这两种方法对于一定尺......
在托卡马克偏滤器区域充入杂质气体是检验偏滤器杂质屏蔽效应的重要手段。利用快速极紫外EUV光谱仪对EAST托克马克装置上开展的偏......
针对EAST前几轮实验中出现的偏滤器DOME板和外靶板间隙区域冷却水管被等离子体烧蚀破坏的问题,提出延伸外靶板石墨瓦结构以扩大打......
用小试样模拟试验测试了不同功率密度下的材料表面温度分布.用热等静压焊接方法制作了钨为表面的模拟偏滤器材料小试样,用25mm的......
根据已有的理论模型,推算出了HL-2A偏压偏滤器的理论电流为1.5kA、偏压电压为200V,并对HL-2A偏压偏滤器做出了初步设计.HL-2A装置......
根据HL-2A装置的结构特点,提出了HL-2A装置偏滤器系统改造的基本方向.对HL-2A极向场线圈系统进行了优化设计,计算了单零平衡位形,......
介绍了EAST超导托卡马克偏滤器的最新冷却模块结构。利用FLUENT有限元软件对不同参数下的模型进行了稳态热分析,定量研究了冷却模块......
采用了两步热等静压法制备W/Cu穿管部件,即先用热等静压(930℃,100MPa,2h)在钨块的孔内壁上覆一层无氧铜作为中间层,然后再用热等静......
应用Solid Works和ANSYS软件设计了自由液态锡表面流体结构模型,计算了初始流速和热通量不同时液态锡的速度变化和温度变化,得到了......
根据ITER朗缪尔探针系统的测量需求开展了探针系统的初步设计和部分研制工作。通过对探针系统测量需求的细化分析,确定了不同等离......
偏滤器作为直接面向等离子体的内部部件之一,其表面承受的热流密度很高。为提高其冷却通道的冷却能力,降低此部件面向等离子体面边......
介绍了EAST超导托卡马克偏滤器的结构和相关分析,并对第一壁材料的导热性能和结构的换热效果进行了实验测试,验证了结构的可靠性。......
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本文用Monte Carlo方法模拟了偏滤器扁平抽气收集板附近区域的氦原子输运。考虑了氦原子被电子碰撞电离,氦原子与等离子体离子之间......
The fluid simulation of Small Size Divertor Tokamak (SSDT) plasma edge by the B2-SOLPS5.0 2D [1] transport code gives th......