The adsorption of hydrogen on W(110) and Fe covered W(110) surfaces

Nahm, Tschang-Uh; Gomer, R.

doi:10.1016/s0039-6028(96)01274-5

Cited by 31 publications

(29 citation statements)

References 15 publications

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“…E W-H 2 ffi 1:4 eV on polycrystalline W [4] and 1.15-1.6 eV on individual planes [8]. The latter has been obtained from H 2 desorption studies and an equilibrium-surface-coverage measurement [9]. Using E W-H 2 ¼ 1:4 eV yields E W-H = 2.95 eV.…”

Section: Discussionmentioning

confidence: 99%

“…Other measurements also provide constraints on any model for this dissociation. Examples are: exposure of clean 6300 K tungsten to a known H 2 flux, followed by measurement of H 2 evolution as the metal temperature (T) is raised [4,8], measurement of surface H concentration [9], surface H diffusion [10], H 2 beam attenuation due to adsorption [11], and H-D exchange reactions on the surface [12]. A few calculations study dissociative adsorption and H 2 desorption on W [13]; in contrast, scores of papers appear every year about these processes on silicon surfaces, e.g., [14] and references therein.…”

Section: Introductionmentioning

confidence: 99%

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Hydrogen dissociation on high-temperature tungsten

Zheng

Gallagher

2006

Surface Science

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Hydrogen dissociation on high-temperature tungsten

Zheng

Gallagher

2006

Surface Science

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“…The concentration profile is also shown for two cases: (1) with a high near-surface concentration resulting from a sluggish re-emission from the surface, and (2) with a lower near-surface concentration resulting from an enhanced re-emission of implanted flux to the plasma. This, in turn, means a reduced driving potential for diffusion into the bulk; (figure provided by G. [403], activation energy for diffusion E m =0.39 eV [403], binding enthalpy of hydrogen to a vacancy Q t =1.1 eV [400,401], enthalpy of adsorption Q a =0.7 eV [404,405] 39 Net carbon erosion rate at the divertor strike-point vs. strike-point heat flux on JET and DIII-D. JET data [110] and DiMES at 1.5 MW·m −2 [521] were obtained with colorimetry. All other DiMES data come from depthmarked insertable probes [480,530].…”

Section: Plasma-edge and Plasma-materials Interaction Issues In Next-smentioning

confidence: 99%

“…[376,399,[403][404][405] appear at the bottom of Table 9 and are reported here just to maintain consistent reference sequential numbering while appending the tables at the end of the section.…”

Section: Insert Tablementioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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“…Thus there are also many literature studies about these materials. [1][2][3][4][5][6][7][8][9] It is interesting to investigate the growth mode of the fcc metal on the bcc single crystal. Al has the fcc structure and W has the bcc structure and their lattice constants are quite different from each other.…”

Section: Introductionmentioning

confidence: 99%

ULTRATHIN Al FILM ON THE W(100) SURFACE

Choi

Kim

2009

Mod. Phys. Lett. B

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We have investigated Al adsorption on the W(100) surface using LEED and low energy Ion Scattering Spectroscopy (ISS). We observe a p(2 × 1) double domain LEED image for the 1.0 ML Al/W(100) surface at annealing temperature 850 • C. We also measured the Al adsorption site at the Al/W(100) -p(2 × 1) surface using ISS. It is found that Al atoms adsorbed at 0.7 ± 0.1Å aside from the center of the bridge sites with a zigzag structure -one atom adsorbs at the right-hand side and next atom at the left-hand side along the [100] direction. The height of the adsorbed Al atoms is determined to be 1.75 ± 0.15Å above the W surface layer. Keywords: Low energy ion scattering; W(100); Al; surface structure; adsorption site. 835 Mod. Phys. Lett. B 2009.23:835-847. Downloaded from www.worldscientific.com by UNIVERSITY OF CALIFORNIA @ DAVIS on 02/08/15. For personal use only.

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The adsorption of hydrogen on W(110) and Fe covered W(110) surfaces

Cited by 31 publications

References 15 publications

Hydrogen dissociation on high-temperature tungsten

Hydrogen dissociation on high-temperature tungsten

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

ULTRATHIN Al FILM ON THE W(100) SURFACE

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