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AbstractAbstract
[en] With the exception of small, simple Langmuir probes, other probes used to diagnose the scrape-off plasma behind the limiter radius or separatrix in tokamaks are usually sufficiently large that they disturb the plasma they are measuring. A theory is presented for recovering the undisturbed plasma parameters from those measured by a large probe in a collisionless scrape-off layer. (orig.)
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Symposium on energy removal and particle control in toroidal devices; Princeton, NJ (USA); 26-29 Jul 1983; CODEN: JNUMA.
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Journal Article
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Journal of Nuclear Materials; ISSN 0022-3115;
; v. 121 p. 36-40

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Chen, Zhong-Ping; Kotschenreuther, Mike; Mahajan, Swadesh; Gerhardt, Stefan, E-mail: chenzhongping@utexas.edu2018
AbstractAbstract
[en] The X-divertor (XD) geometry in NSTX-U is demonstrated, via SOLPS simulations, to perform better than the standard divertor (SD); in particular, it allows detachment at a lower upstream density and stabilizes the detachment front near the target, away from the main X-point. Consequently a stable detached operation becomes possible—the localization near the plate allows a vast reduction of heat fluxes without degrading the core plasma. Indeed, it is confirmed by our simulation that at similar states of detachment the XD outperforms the SD by reducing the heat fluxes to the target and maintaining higher upstream temperatures, resulting in scrape-off layers that are more favorable for advanced tokamak operation. These advantages are attributed to the unique geometric characteristics of XD—poloidal flaring near the target. (paper)
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Available from http://dx.doi.org/10.1088/1741-4326/aaa5ca; Country of input: International Atomic Energy Agency (IAEA)
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Stegmeir, A.; Coster, D.; Maj, O.; Ross, A., E-mail: andreas.stegmeir@ipp.mpg.de
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
AbstractAbstract
[en] Full text: The complex geometry in the edge and scrape-off layer poses a challenge to simulations of magnetically confined plasmas, since the usually employed field/flux-aligned coordinates become singular on the separatrix/X-point. A field line map approach (see also flux-coordinate independent approach) offers a promising solution to these problems. The approach is based on a cylindrical grid, which is Cartesian within poloidal planes, and the characteristic flute mode property (kǁ ≪ k⊥) of structures is exploited computationally via grid sparsification in the toroidal direction. A field line following discretization for parallel operators is then required, which includes field line tracing and interpolation and/or discrete integration. Advanced numerical techniques were developed in order to overcome the critical issue of numerical diffusion and the treatment of boundaries. The whole concept is implemented in the code GRILLIX, which features flexibility in treating different and complex geometries, especially with separatrix and X-point(s). Simulations based on a simplified turbulence model (Hasegawa–Wakatani) elucidate the effect of the X-point on turbulent structures. Furthermore, a full-f drift reduced Braginskii model, where the Boussinesq approximation is dropped, is employed for studies on blob propagation in the scrape-off layer. (author)
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International Atomic Energy Agency, Division of Physical and Chemical Sciences, Vienna (Austria); 935 p; 3 May 2018; p. 630; FEC 2016: 26. IAEA Fusion Energy Conference; Kyoto (Japan); 17-22 Oct 2016; IAEA-CN--234-0215; Available as preprint from https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202016/fec2016-preprints/preprint0215.pdf; Abstract only
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AbstractAbstract
[en] A density clamp is observed in DITE tokamak with neutral beam injection heating. Measurements in the scrape-off plasma are described which show an increase in the particle flux to the limiters during injection. This is sufficient to account for the density clamp without requiring a change in the recycling coefficient. (author)
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Letter-to-the-editor.
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Journal Article
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Nuclear Fusion; ISSN 0029-5515;
; v. 23(7); p. 933-935

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AbstractAbstract
[en] Visual inspection of the full poloidal ring limiters of Alcator C identifies two directionally asymmetric damage regions at the high field side of the plasma: At the top location on the electron side (as defined by plasma current) and at the bottom location on the ion side. We report direct measurements of edge plasma parameters in the SOL plasma on the top location using Janus, a two-sided, multi-diagnostic edge probe. Higher ion and electron temperatures and densities at the probe location occur on the electron side under standard operating conditions. The degree of asymmetry cannot be explained by limiter configuration alone, but the direction of the toroidal field and variation of the plasma horizontal position, change the magnitude of asymmetry. Mechanisms that may cause the directional asymmetries include prallel plasma flow and asymmetric perpendicular transport into the collecting flux tubes. Measurements made by DENSEPACK, a full poloidal array of Langmuir probes, show that strong poloidal asymmetries in both plasma density and electron temperature in the scrape-off region of Alcator C exist. Such asymmetries may arise from asymmetric perpendicular transport and/or act to drive plasma flows along field lines. (orig.)
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7. international conference on plasma-surface interactions in controlled fusion devices (PSI-7); Princeton, NJ (USA); 5-9 May 1986; CONTRACT DE-AC02-78ET51013
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Canik, John M.; Tang, X.-Z.
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Funding organisation: USDOE Office of Science - SC (United States)2017
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Funding organisation: USDOE Office of Science - SC (United States)2017
AbstractAbstract
[en] While the sensitivity of the scrape-off layer and divertor plasma to the highly uncertain cross-field transport assumptions is widely recognized, the plasma is also sensitive to the details of the plasma-material interface (PMI) models used as part of comprehensive predictive simulations. Here in this paper, these PMI sensitivities are studied by varying the relevant sub-models within the SOLPS plasma transport code. Two aspects are explored: the sheath model used as a boundary condition in SOLPS, and fast particle reflection rates for ions impinging on a material surface. Both of these have been the study of recent high-fidelity simulation efforts aimed at improving the understanding and prediction of these phenomena. It is found that in both cases quantitative changes to the plasma solution result from modification of the PMI model, with a larger impact in the case of the reflection coefficient variation. Finally, this indicates the necessity to better quantify the uncertainties within the PMI models themselves, and perform thorough sensitivity analysis to propagate these throughout the boundary model; this is especially important for validation against experiment, where the error in the simulation is a critical and less-studied piece of the code-experiment comparison.
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OSTIID--1341530; AC05-00OR22725; AC52-06NA25396; Available from http://www.osti.gov/pages/biblio/1341530; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period
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Journal Article
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Fusion Science and Technology; ISSN 1536-1055;
; v. 71(1); p. 103-109

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AbstractAbstract
[en] Turbulent fluctuations in the tokamak scrape-off layer (SOL) generally display an intermittent character with strongly non-Gaussian amplitude statistics. Spatiotemporal imaging of turbulent fluctuations at the outer midplane revealed the propagation of turbulent field-aligned filament structures, which peel-off the separatrix region and propagate radially outwards to the wall A newly installed Dalpha turbulent imaging diagnostic measuring in the strong magnetic shear region close to the lower X-point in Alcator C-Mod allows for a detailed comparison of the properties of turbulent fluctuations between the outer midplane and X-point region. In contrast to the mostly circular cross-sections of turbulent structures at the midplane, structures are strongly elongated in radial direction at the X-point view. The elongation is consistent with magnetic flux surface expansion, which strongly suggests the filamentary nature of structures along the magnetic field. The X-point imaging data are directly compared to simultaneous fluctuation measurements obtained from an array of Dalpha diode views arranged radially and poloidally at the outer midplane. The statistical properties of fluctuations and the propagation speed of spatiotemporal fluctuations structures in the two regions are compared.
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2009 DPG Spring meeting with the divisions of plasma physics, short-time period physics, extraterrestrial physics; DPG-Fruehjahrstagung 2009 der Fachverbaende Plasmaphysik, Kurzzeitphysik, Extraterrestrische Physik; Greifswald (Germany); 30 Mar - 2 Apr 2009; Available from http://www.dpg-verhandlungen.de; Session: P 16.14 Mi 17:30; No further information available; Also available as printed version: Verhandlungen der Deutschen Physikalischen Gesellschaft v. 44(6)
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Verhandlungen der Deutschen Physikalischen Gesellschaft; ISSN 0420-0195;
; CODEN VDPEAZ; (Greifswald 2009 issue); [1 p.]

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AbstractAbstract
[en] Using a reciprocating Retarding Field Analyser (RFA), Scrape-Off Layer (SOL) modifications were investigated on ASDEX-Upgrade during heating with waves in the Ion Cyclotron Range of Frequencies (ICRF), suspected for enhanced impurity production in this all-metal machine. Two quantities involved in the sputtering were measured: the current I(slit) on a saturated slit plate, proportional to the parallel ion flux and the mean parallel energy < WI>t of collected ions, averaged over many RF cycles. Combining multiple RFA reciprocations over a scan of q95 provided 2D poloidal/radial resolution. In the outer SOL a localized RF-perturbed zone was evidenced on the RFA side magnetically connected to an active ICRF antenna. A flat 2D I(slit) pattern surrounded by steep gradients was observed, correlatively with < WI>t exceeding 150 eV. The centre of the zone is connected radially slightly behind the leading edge of antenna side limiters, with a radial extension up to ±2 cm. The zone is broadest and < WI>t is largest near the bottom of the active antenna. This is interpreted as a zone of local plasma biasing via sheath rectification, creating density convection around it. The I(slit) pattern is qualitatively consistent with simple considerations about ExB particle convection. (authors)
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2014; 4 p; Angelo A. Tuccillo and Silvio Ceccuzzi; Melville, New York (United States); 20. Topical Conference on Radiofrequency Power in Plasmas; Sorrento (Italy); 25-28 Jun 2013; ISBN 978-0-7354-1210-1;
; Available from doi: http://dx.doi.org/10.1063/1.4864537; Country of input: France

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Book
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Rubino, G.; Ambrosino, R.; Calabrò, G.; Pericoli Ridolfini, V.; Viola, B., E-mail: giulio.rubino@enea.it2017
AbstractAbstract
[en] Highlights: • A benchmark of two plasma edge codes, TECXY and EDGE2D-EIRENE, is presented. • A preliminary study of a DEMO scenario is performed assuming simplified hypotheses. • The two codes predict different density, temperature and pressure target profiles. • The predicted power density and total power reaching the divertor are similar. • In well attached plasma conditions TECXY could be used for fast scoping studies. - Abstract: In this contribution a benchmark of the 2D edge codes TECXY and EDGE2D-EIRENE is presented. A conventional DEMO scenario is considered by assuming a simplified geometry, with the target plates perpendicular to the separatrix, and a pure Deuterium plasma. Despite the different models adopted in the two codes, mainly related to the description of the neutral dynamics and to the different boundary conditions, the results show a good match both in terms of power load profiles on the outer target and predicted trends for global quantities. A scan in density and in diffusion coefficients is performed in order to identify the characteristic conditions and the different regimes of the SOL. Comparable values and similar dependency of the global quantities as a function of the power decay length is also observed.
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PSI-22: 22. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices; Rome (Italy); 30 May - 3 Jun 2016; S2352179116302782; Available from http://dx.doi.org/10.1016/j.nme.2016.11.004; © 2016 The Authors. Published by Elsevier Ltd.; Country of input: International Atomic Energy Agency (IAEA)
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Nuclear Materials and Energy; ISSN 2352-1791;
; v. 12; p. 864-868

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Mijin, S; Kingham, R J; Militello, F; Newton, S; Omotani, J, E-mail: stefan.mijin14@imperial.ac.uk2020
AbstractAbstract
[en] We present the first parallel electron transport results obtained using the newly developed 1D transport code SOL-KiT. With the capability to switch between consistent kinetic and fluid models for the electrons, we explore and report the differences in both equilibrium and transient simulations. Significant kinetic effects are found during transients, especially in the behaviour of the electron sheath heat transmission coefficient, which shows up to an eightfold increase. Equilibria are obtained for an input power scan with parameters relevant to medium size tokamaks. Detached equilibria are found to persist to higher input powers when electrons are treated kinetically. Furthermore, non-monotonic behaviour of the electron sheath heat transmission coefficient is observed in the power scan, with values being up to 40% above the classical value. We discuss the implications of the presented results to potential modelling decisions, as well as possible extensions to the used model. (paper)
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Available from http://dx.doi.org/10.1088/1361-6587/ab9b39; Country of input: International Atomic Energy Agency (IAEA)
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