Observations of orientation dependence of surface morphology in tungsten implanted by low energy and high flux D plasma

Xu, Huaping; Zhang, Yubin; Yuan, Yue; Fu, Baoqin; Godfrey, A.; Temmerman, G. De; Liu, W.; Huang, Xiaoxu

doi:10.1016/j.jnucmat.2013.07.062

Cited by 57 publications

(28 citation statements)

References 17 publications

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“…As discussed, this chemisorbed layer can act as a protective layer preventing direct penetration. Finally, our results shed light on previously reported strong surface modifications of tungsten during exposure to deuterium plasmas at biased conditions [27,28] as opposed to the absence of such modifications for self-bias conditions. The surface modifications can be related to an oversaturation of tungsten with deuterium originating in the direct penetration.…”

Section: Cannot Explain Thissupporting

confidence: 78%

Strongly Reduced Penetration of Atomic Deuterium in Radiation-Damaged Tungsten

et al. 2013

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Section: Cannot Explain Thissupporting

confidence: 78%

Strongly Reduced Penetration of Atomic Deuterium in Radiation-Damaged Tungsten

et al. 2013

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“…The correlation of these structures with grain orientation is obvious. Xu et al [40,41] reported about similar structures on tungsten exposed to D plasma with very high deuteron flux. They determined the correlation between appearance and specific grain orientation.…”

Section: Spherical Blistersmentioning

confidence: 90%

“…The comparison of morphological modifications for different fluxes indicates the presence of more hydrogen loading-induced damaging processes at higher fluxes, e.g., the appearance of volcano-like extrusions with cracking and distortions inside single grains [11][12][13][14][15]25] as well as the nanostructures on the surface [3,40,41]. Other hydrogen loading-induced features, namely the stepped flattopped extrusions, can already be created at moderate flux, and their appearance exhibits a strong dependence on the W grade.…”

Section: Discussionmentioning

confidence: 99%

“…Furthermore, due to the very high flux at Pilot-PSI smaller tiny extrusions with cracks and distortions below (lateral size of ~250 nm) occur [25,39] as well as surface structuring on the nanometre scale (tens of nm) [3,40,41]. These surface modifications, especially the extrusions, point to further damaging at higher deuteron fluxes.…”

Section: Spherical Blistersmentioning

confidence: 99%

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Deuterium retention and morphological modifications of the surface in five grades of tungsten after deuterium plasma exposure

Balden

Manhard

Elgeti

2014

Journal of Nuclear Materials

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Five tungsten (W) grades were simultaneously exposed to deuterium (D) plasma with ) is attributed only to the different properties of each W grade. Spherical blisters and stepped flat-topped extrusions are observed depending on the W grade. These modifications are interpreted as an indication for hydrogen loading-induced damaging. The exposure conditions and W grades were chosen to allow a comparison between published data sets.

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“…The appearance of blisters is influenced by many different parameters, e.g. sample temperature [6,7], ion energy [8], ion flux [9,10], ion fluence [8], grain orientation [11], material grade [12] and surface finish [13]. As large as the parameter space which determines blistering, as large is the variety of shapes in which blisters occur.…”

Section: Introductionmentioning

confidence: 99%

Influence of near-surface blisters on deuterium transport in tungsten

et al. 2017

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The effect of near-surface blisters on deuterium transport in tungsten is studied by means of nuclear reaction analysis (NRA) and scanning electron microscopy (SEM). Gentle deuterium plasma loading of different durations and subsequent NRA depth profiling is performed in heavily pre-blistered and unblistered areas on self-damaged tungsten samples.Comparison of the deuterium depth profiles reveals a considerable reduction of the deuterium transport into the bulk due to the presence of near-surface blisters. SEM and NRA results identify the enhanced re-emission of deuterium from the sample due to open blisters as the underlying mechanism which reduces the deuterium flux into the bulk. Based on a simple analytical hydrogen retention model, the re-emitted deuterium flux by open blisters in the here conducted experiment, is determined to be 80 % of the implanted deuterium flux. In addition, the deuterium flux into the bulk is reduced by 60 % compared to the unblistered case. As a consequence, deuterium retention studies carried out under blister-facilitating conditions should account for surface morphology which reduce the deuterium uptake.

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Observations of orientation dependence of surface morphology in tungsten implanted by low energy and high flux D plasma

Cited by 57 publications

References 17 publications

Strongly Reduced Penetration of Atomic Deuterium in Radiation-Damaged Tungsten

Strongly Reduced Penetration of Atomic Deuterium in Radiation-Damaged Tungsten

Deuterium retention and morphological modifications of the surface in five grades of tungsten after deuterium plasma exposure

Influence of near-surface blisters on deuterium transport in tungsten

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