英国物理学会
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作者:G.-N. Luo , G.H. Liu ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (6)IOP
摘要:The first EAST (Experimental Advanced Superconducting Tokamak) plasma ignited in 2006 with non-actively cooled steel plates as the plasma-facing materials and components (PFMCs) which were then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks in 2...
作者:G.-N. Luo , C. Li ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (11)IOP
摘要:The thermal shock behaviour of blister-covered W surfaces during combined steady-state/pulsed plasma loading was studied by scanning electron microscopy and electron backscatter diffraction. The W samples were first exposed to steady-state D plasma to induce blisters on the surfa...
作者:... Q.M. Hu , Jun-Ling Chen , G.-N. Luo
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (2)IOP
摘要:We have performed systematic first-principles calculations to predict the interaction between transition metal (TM) solutes and hydrogen in the interstitial site as well as the vacancy in tungsten. We showed that the site preference of the hydrogen atom is significantly infl...
作者:G.-N. Luo , G.-H. Lu
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (3)IOP
摘要:Surface damage and structure evolution of the full tungsten ITER divertor under transient heat loads is a key concern for component lifetime and plasma operations. Recrystallization caused by transients and steady-state heat loads can lead to degradation of the material prop...
作者:... C.S. Liu , Jun-Ling Chen , G.-N. Luo
来源:[J].Nuclear Fusion(IF 2.734), 2016, Vol.56 (10)IOP
摘要:While inert gas seeding to improve energy confinement has been successfully applied in many tokamak experiments, questions remain as to the irradiation effects of inert gases on tungsten. In this paper, we have systematically investigated the clustering behaviors of the iner...
作者:... Q.F. Fang , J.L. Chen , G.-N. Luo
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (8)IOP
摘要:The formation of transmutation solute-rich precipitates has been reported to seriously degrade the mechanical properties of tungsten in a fusion environment. However, the underlying mechanisms controlling the formation of the precipitates are still unknown. In this study, fi...
作者:... Yunfeng Liang , Jun-Ling Chen , G.-N. Luo
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (11)IOP
摘要:Radiation damage not only seriously degrades the mechanical properties of tungsten (W) but also enhances hydrogen retention in the material. Introducing a large amount of defect sinks, e.g. grain boundaries (GBs) is an effective method for improving radiation-resistance of W. How...
作者:... Fang Ding , G.-N. Luo , Chang-An Chen
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (12)IOP
摘要:We have carried out systematic first-principles total energy and vibration spectrum calculations to investigate the finite-temperature H dissolution behaviors in tungsten and molybdenum, which are considered promising candidates for the first wall in nuclear fusion reactors. The ...
作者:G.-N. Luo , X.Z. Gong ...
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (5)IOP
摘要:The active feedback control of radiated power to prevent divertor target plates overheating during long-pulse operation has been developed and implemented on EAST. The radiation control algorithm, with impurity seeding via a supersonic molecular beam injection (SMBI) system,...
作者:... T. Zhu , F. Ding , G.-N. Luo
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (5)IOP
摘要:Helium (He) effects on deuterium (D) retention in reduced activation ferritic/martensitic steel (RAFMs) have been studied by high-energy He ion pre-injection and following D plasma exposure. He-damaged layers at the surface and inside the material bulk are induced by 3.5 MeV He i...

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