Počet záznamů: 1
Erosion, screening, and migration of tungsten in the JET divertor
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SYSNO ASEP 0522776 Druh ASEP J - Článek v odborném periodiku Zařazení RIV J - Článek v odborném periodiku Poddruh J Článek ve WOS Název Erosion, screening, and migration of tungsten in the JET divertor Tvůrce(i) Brezinsek, S. (DE)
Kirschner, A. (DE)
Mayer, M. (DE)
Baron-Wiechec, A. (GB)
Borodkina, Irina (UFP-V)
Borodin, D. (DE)
Coffey, I. (GB)
Coenen, J. (DE)
den Harder, N. (DE)
Eksaeva, A. (DE)
Guillemaut, C. (PT)
Heinola, K. (FI)
Huber, A. (DE)
Huber, V. (DE)
Imríšek, Martin (UFP-V) RID
Jachmich, S. (US)
Pawelec, E. (PL)
Rubel, M. (SE)
Krat, S. (DE)
Sergienko, G. (DE)
Matthews, G. F. (GB)
Meigs, A.G. (GB)
Wiesen, S. (DE)
Widdowson, A. (GB)Celkový počet autorů 24 Číslo článku 096035 Zdroj.dok. Nuclear Fusion. - : Institute of Physics Publishing - ISSN 0029-5515
Roč. 59, č. 9 (2019)Poč.str. 24 s. Jazyk dok. eng - angličtina Země vyd. AT - Rakousko Klíč. slova ERO modelling ; erosion and deposition ; ITER divertor ; jet ; Tungsten divertor ; W spectroscopy Obor OECD Fluids and plasma physics (including surface physics) Způsob publikování Omezený přístup Institucionální podpora UFP-V - RVO:61389021 UT WOS 000478620300002 EID SCOPUS 85072087051 DOI 10.1088/1741-4326/ab2aef Anotace The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles, determines the lifetime of plasma-facing components as well as impacting on plasma performance by the influx of W into the confined region. The screening of W by the divertor and the transport of W in the plasma determines largely the W content in the plasma core, but the W source strength itself has a vital impact on this process. The JET tokamak experiment provides access to a large set of W erosion-determining parameters and permits a detailed description of the W source in the divertor closest to the ITER one: (i) effective sputtering yields and fluxes as function of impact energy of intrinsic (Be, C) and extrinsic (Ne, N) impurities as well as hydrogenic isotopes (H, D) are determined and predictions for the tritium (T) isotope are made. This includes the quantification of intra-and inter-edge localised mode (ELM) contributions to the total W source in H-mode plasmas which vary owing to the complex flux compositions and energy distributions in the corresponding phases. The sputtering threshold behaviour and the spectroscopic composition analysis provides an insight in the dominating species and plasma phases causing W erosion. (ii) The interplay between the net and gross W erosion source is discussed considering (prompt) re-deposition, thus, the immediate return of W ions back to the surface due to their large Larmor radius, and surface roughness, thus, the difference between smooth bulk-W and rough W-coating components used in the JET divertor. Both effects impact on the balance equation of local W erosion and deposition. (iii) Post-mortem analysis reveals the net erosion/deposition pattern and the W migration paths over long periods of plasma operation identifying the net W transport to remote areas. This W transport is related to the divertor plasma regime, e.g. attached operation with high impact energies of impinging particles or detached operation, as well as to the applied magnetic configuration in the divertor, e.g. close divertor with good geometrical screening of W or open divertor configuration with poor screening. JET equipped with the ITER-like wall (ILW) provided unique access to the net W erosion rate within a series of 151 subsequent H-mode discharges (magnetic field: T, plasma current: MA, auxiliary power MW) in one magnetic configuration accumulating 900 s of plasma with particle fluences in the range of 5-in the semi-detached inner and attached outer divertor leg. The comparison of W spectroscopy in the intra-ELM and inter-ELM phases with post-mortem analysis of W marker tiles provides a set of gross and net W erosion values at the outer target plate. ERO code simulations are applied to both divertor leg conditions and reproduce the erosion/deposition pattern as well as confirm the high experimentally observed prompt W re-deposition factors of more than 95% in the intra-and inter-ELM phase of the unseeded deuterium H-mode plasma. Conclusions to the expected divertor conditions in ITER as well as to the JET operation in the DT plasma mixture are drawn on basis of this unique benchmark experiment. Pracoviště Ústav fyziky plazmatu Kontakt Vladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975 Rok sběru 2020 Elektronická adresa https://iopscience.iop.org/article/10.1088/1741-4326/ab2aef/pdf
Počet záznamů: 1