Zobrazeno 1 - 10
of 47
pro vyhledávání: '"C. H. Skinner"'
Autor:
T Abrams, J G Guterl, S Abe, D C Donovan, I Bykov, C A Johnson, J H Nichols, J D Elder, D A Ennis, S D Loch, D L Rudakov, G Sinclair, C H Skinner, P C Stangeby, D M Thomas, E A Unterberg, W R Wampler
Publikováno v:
Materials Research Express, Vol 10, Iss 12, p 126503 (2023)
Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to inform the lifetime of tungsten plasma-facing components in ITER and other future devices. Various experi
Externí odkaz:
https://doaj.org/article/0a7001fe3a7a45338e386899869cccc0
Autor:
C. H Skinner, F. Bedoya, F. Scotti, J.P. Allain, W. Blanchard, D. Cai, M. Jaworski, B.E. Koel
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 744-748 (2017)
Boronization has been effective in reducing plasma impurities and enabling access to higher density, higher confinement plasmas in many magnetic fusion devices. The National Spherical Torus eXperiment, NSTX, has recently undergone a major upgrade to
Externí odkaz:
https://doaj.org/article/4f7f2d8e843245028bab58212906917d
Publikováno v:
Physics of Plasmas. 29:102503
We present a computational investigation of the dependence of material erosion on the incident ion angle at rough graphite and silicon carbide divertor surfaces. Ion angle distributions (IADs) for D plasmas at NSTX-U and DIII-D divertors were calcula
Autor:
F. Bedoya, Filippo Scotti, V. A. Soukhanovskii, Klaus Schmid, M. A. Jaworski, C. H. Skinner, J.H. Nichols
Publikováno v:
Nuclear Materials and Energy
Nuclear Materials and Energy, Vol 19, Iss, Pp 445-450 (2019)
Nuclear Materials and Energy, Vol 19, Iss, Pp 445-450 (2019)
Boronization is commonly utilized in tokamaks to suppress intrinsic impurities, most notably oxygen from residual water vapor. However, this is a temporary solution, as oxygen levels typically return to pre-boronization levels following repeated plas
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d0eeaf5bd0fb0ee2b897353a1179174e
https://hdl.handle.net/21.11116/0000-0003-C2ED-721.11116/0000-0003-C2EF-5
https://hdl.handle.net/21.11116/0000-0003-C2ED-721.11116/0000-0003-C2EF-5
Publikováno v:
Journal of Nuclear Materials. 463:276-279
As fusion reactors scale up in size, power, and duty cycle, the quantity of material eroded from the plasma-facing components (PFCs) will rise to levels far above those seen in prior experiments, and could hinder proper operation. While reactor scena
Autor:
Tetsuo Tanabe, R. P. Doerner, N. Bekris, J. Roth, C. H. Skinner, A.A. Haasz, J. P. Coad, R. E. H. Clark, R. A. Causey, J.W. Davis, M. Mayer, V.Kh. Alimov, A. Pisarev
Publikováno v:
Scopus-Elsevier
Fusion Science and Technology
Fusion Science and Technology
Management of tritium inventory remains one of the grand challenges in the development of fusion energy, and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the Internationa
Autor:
C H Skinner
Publikováno v:
Canadian Journal of Physics. 86:285-290
Fusion-energy development has reached an exciting stage with the agreement by seven nations, representing over half the world population, to build the International Thermonuclear Experimental Reactor (ITER) and demonstrate the scientific and technolo
Publikováno v:
Journal of Nuclear Materials. :1461-1465
Methods to measure the inventory of dust particles and to remove dust if it approaches safety limits will be required in next-step tokamaks. A novel electrostatic dust detector, based on a fine grid of interlocking circuit traces, biased to 30 or 50
Publikováno v:
Journal of Nuclear Materials. 346:266-271
The inventory of dust in next-step magnetic fusion devices will be regulated for safety reasons, however diagnostics to measure in-vessel dust are still in their infancy. Advances in dust particle detection on remote surfaces are reported. Grids of i
Autor:
R Maingi, M G Bell, R E Bell, J Bialek, C Bourdelle, C E Bush, D S Darrow, E D Fredrickson, D A Gates, M Gilmore, T Gray, T R Jarboe, D W Johnson, R Kaita, S M Kaye, S Kubota, H W Kugel, B P LeBlanc, R J Maqueda, D Mastrovito, S S Medley, J E Menard, D Mueller, B A Nelson, M Ono, F Paoletti, H K Park, S F Paul, T Peebles, Y-K M Peng, C K Phillips, R Raman, A L Rosenberg, A L Roquemore, P M Ryan, S A Sabbagh, C H Skinner, V A Soukhanovskii, D Stutman, D W Swain, E J Synakowski, G Taylor, J Wilgen, J R Wilson, G A Wurden, S J Zweben, the NSTX Team
Publikováno v:
Plasma Physics and Controlled Fusion. 45:657-669
The National Spherical Torus Experiment (NSTX) is a low aspect-ratio fusion research facility whose research goal is to make a determination of the attractiveness of the spherical torus concept in the areas of high-β stability, confinement, current