Microscopic and macroscopic damage in metals exposed to LHD divertor plasmas

Tokitani, M.; Miyamoto, M.; Koga, D.; Tokunaga, Kazutoshi; Fujiwara, Tadashi; Yoshida, N.; Masuzaki, S.; Ashikawa, N.; Morisaki, T.; Shoji, M.; Komori, A.

doi:10.1016/j.jnucmat.2004.07.054

Cited by 22 publications

(29 citation statements)

References 9 publications

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“…The ion impact energy is in the order of tens to hundreds of eV. These exposure parameters fall into the parameter range of blistering studies in laboratory experiments [1][2][3][4][5][6][7][8][9][10][11][12][13].…”

Section: Methodsmentioning

confidence: 99%

“…Blistering of tungsten (W) materials -caused by the large transient hydrogen supersaturation in the metal -is a phenomenon well documented in laboratory experiments [1][2][3][4][5][6][7], but only sparsely observed in fusion devices [8,9]. The laboratory experiments indicate that the tungsten grade and the surface quality, e.g., polished or technical surface, as well as the impurity content in the incident hydrogen flux play a role in appearance and abundance of blistering and other morphological changes [10,11,12,13].…”

Section: Introductionmentioning

confidence: 99%

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Blistering and re-deposition on tungsten exposed to ASDEX Upgrade divertor plasma

Balden

Rohde

Lindig

et al. 2013

Journal of Nuclear Materials

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A well-polished and pre-characterised polycrystalline tungsten specimen was exposed to the outer divertor plasma of ASDEX Upgrade close to the strike point for 510 discharges in the campaign 2011 by using the divertor manipulator system. The exposure with a mixture of hydrogen and various impurities leads to blistering. The exposure parameters are comparable to those used in blistering studies under laboratory conditions. Furthermore, spherical dust particles formed by the strong plasma contact were transported and deposited onto the nearly vertically orientated target plates, i.e., the analysed specimen. In subsequent discharges, these particles were partly eroded and a microscopic pattern of layered deposits was formed around them with an elongation rotated ~40° to the projected B field line direction. PACS: 28.52 Fa, 52.40 Hf, 68.37 Hk, 82.80 Ej

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Blistering and re-deposition on tungsten exposed to ASDEX Upgrade divertor plasma

Balden

Rohde

Lindig

et al. 2013

Journal of Nuclear Materials

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“…Tungsten based materials are potential candidates of the plasma facing materials. In our previous study, details of the microscopic and macroscopic damage of tungsten exposed to the LHD divertor plasmas have been studied by using several analytical techniques [1]. However, in addition to the studies on the damage, characterization of the plasma particles injected in the divertor tiles is very important for the controls of impurities and hydrogen isotopes in the vacuum vessel.…”

Section: Introductionmentioning

confidence: 99%

Retention properties of plasma particles in tungsten exposed to LHD divertor plasmas

Tokitani¹,

Miyamoto²,

Tokunaga³

et al. 2007

Journal of Nuclear Materials

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“…We note that tests of candidate metals exposed to high heat flux have results in small-scale surface roughness that may enhance the emissivity 33,34,35 . A spatial calibration is also necessary to make proper use of the data.…”

Section: A Ir Calibrationmentioning

confidence: 93%

“…[ ] [34] According to Ref. 13, for the values of x we need for IRTV, keeping the first 10 terms of the sum should provide 10 significant figures or more of accuracy.…”

Section: B Estimating Radiated Blackbody Power On An Ir Camera Pixelmentioning

confidence: 99%

Visible and Infrared Optical Design for the ITER Upper Ports

Lasnier¹,

Seppala²,

Morris³

et al. 2007

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This document contains the results of an optical design scoping study of visible-light and infrared optics for the ITER 1 upper ports, performed by LLNL under contract for the US ITER Project Office. ITER is an international collaboration to build a large fusion energy tokamak with a goal of demonstrating net fusion power for pulses much longer than the energy confinement time. At the time of this report, six of the ITER upper ports are planned to each to contain a camera system for recording visible and infrared light, as well as other diagnostics. The performance specifications for the temporal and spatial resolution of this system are shown in the Section II, Functional Specifications. We acknowledge a debt to Y. Corre and co-authors of the CEA Cadarache report "ITER wide-angle viewing and thermographic and visible system" 2 . Several of the concepts used in this design are derived from that CEA report.The infrared spatial resolution for optics of this design is diffraction-limited by the size of the entrance aperture, at lower resolution than listed in the ITER diagnostic specifications. The size of the entrance aperture is a trade-off between spatial resolution, optics size in the port, and the location of relay optics. The signal-to-noise ratio allows operation at the specified time resolutions.3

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Microscopic and macroscopic damage in metals exposed to LHD divertor plasmas

Cited by 22 publications

References 9 publications

Blistering and re-deposition on tungsten exposed to ASDEX Upgrade divertor plasma

Blistering and re-deposition on tungsten exposed to ASDEX Upgrade divertor plasma

Retention properties of plasma particles in tungsten exposed to LHD divertor plasmas

Visible and Infrared Optical Design for the ITER Upper Ports

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