Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. (August 2017)
- Record Type:
- Journal Article
- Title:
- Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. (August 2017)
- Main Title:
- Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade
- Authors:
- Brezinsek, S.
Hakola, A.
Greuner, H.
Balden, M.
Kallenbach, A.
Oberkofler, M.
De Temmerman, G.
Douai, D.
Lahtinen, A.
Böswirth, B.
Brida, D.
Caniello, R.
Carralero, D.
Elgeti, S.
Krieger, K.
Mayer, H.
Meisl, G.
Potzel, S.
Rohde, V.
Sieglin, B.
Terra, A.
Neu, R.
Linsmeier, Ch. - Abstract:
- Abstract: Tungsten (W) will be used as material for plasma-facing components (PFCs) in the divertor of ITER and interact with Helium (He) ions either from initial He plasma operation or from Deuterium-Tritium (DT) fusion reactions in the active operation phase. Laboratory experiments reported that in a specific operational window of impact energy, ion fluence, and surface temperature ( Ein ≥ 20 eV, ϕ ≥ 1 × 10 24 He + m B t = 2.5 T, I p = 0.8 M A, P a u x ≃ 8.0 M W Tsurf ≥ 1000 K) a modification of W surfaces occurs resulting in the formation of He-induced W nanostructures. Experiments in ASDEX Upgrade H-mode plasmas ( E i n = 37 k e V T, ϕ ≃ 0.75 × 10 24 H e 0 m − 2 MA, Paux ≃ 8.0 MW) in He have been carried out to investigate in detail (a) the potential growth of W nanostructures on pre-damaged W samples incorporating He nanobubbles, and (b) the potential ELM-induced erosion of W nanostructure. Both W surface modifications were generated artificially in the GLADIS facility by He bombardment of W samples at ϕ ≃ 1 × 10 24 H e 0 m − 2 keV (a) to ϕ ≃ 0.75 × 10 24 He 0 m ϕ ≃ 1.6 × 10 24 H e + m − 2 at Tsurf ≃ 1800 K and (b) ϕ ≃ 1 × 10 24 He 0 m − 2 at Tsurf ≃ 2300 K prior to exposure in the divertor manipulator of ASDEX Upgrade. Though in part (a) conditions of W nanostructure growth with a total He ion fluence of ϕ ≃ 1.6 × 10 24 He + m − 2 and peak He ion impact energies above 150 eV were met, no growth could be detected. In part (b) lower density plasmas with moreAbstract: Tungsten (W) will be used as material for plasma-facing components (PFCs) in the divertor of ITER and interact with Helium (He) ions either from initial He plasma operation or from Deuterium-Tritium (DT) fusion reactions in the active operation phase. Laboratory experiments reported that in a specific operational window of impact energy, ion fluence, and surface temperature ( Ein ≥ 20 eV, ϕ ≥ 1 × 10 24 He + m B t = 2.5 T, I p = 0.8 M A, P a u x ≃ 8.0 M W Tsurf ≥ 1000 K) a modification of W surfaces occurs resulting in the formation of He-induced W nanostructures. Experiments in ASDEX Upgrade H-mode plasmas ( E i n = 37 k e V T, ϕ ≃ 0.75 × 10 24 H e 0 m − 2 MA, Paux ≃ 8.0 MW) in He have been carried out to investigate in detail (a) the potential growth of W nanostructures on pre-damaged W samples incorporating He nanobubbles, and (b) the potential ELM-induced erosion of W nanostructure. Both W surface modifications were generated artificially in the GLADIS facility by He bombardment of W samples at ϕ ≃ 1 × 10 24 H e 0 m − 2 keV (a) to ϕ ≃ 0.75 × 10 24 He 0 m ϕ ≃ 1.6 × 10 24 H e + m − 2 at Tsurf ≃ 1800 K and (b) ϕ ≃ 1 × 10 24 He 0 m − 2 at Tsurf ≃ 2300 K prior to exposure in the divertor manipulator of ASDEX Upgrade. Though in part (a) conditions of W nanostructure growth with a total He ion fluence of ϕ ≃ 1.6 × 10 24 He + m − 2 and peak He ion impact energies above 150 eV were met, no growth could be detected. In part (b) lower density plasmas with more pronounced type I ELMs, carrying energetic He ions in the keV range, were executed with the strike-line positioned on 2 µm thick W nanostructure accumulating a fluence of ϕ ≃ 0.8 × 10 24 He + m − 2 . Post-mortem analysis revealed that co-deposition by predominantly W, and Boron (B), eroded at the main chamber wall and transported into the divertor, took place on all W samples. Erosion of W nanostructure or its formation was hindered by the fact that the outer divertor at the location of the samples was turned under these He plasma conditions into a net deposition zone by W, B and Carbon (C) ions. The surface morphology with large roughness and effective surface area act as a catcher for the impinging impurities. Thus, apart from operation in the existence diagram of W nanostructure with respect to Tsurf, ϕ, and Ein, also the impinging impurity flux contribution needs to be considered in predictions concerning the formation of W nanostructures. … (more)
- Is Part Of:
- Nuclear materials and energy. Volume 12(2017)
- Journal:
- Nuclear materials and energy
- Issue:
- Volume 12(2017)
- Issue Display:
- Volume 12, Issue 2017 (2017)
- Year:
- 2017
- Volume:
- 12
- Issue:
- 2017
- Issue Sort Value:
- 2017-0012-2017-0000
- Page Start:
- 575
- Page End:
- 581
- Publication Date:
- 2017-08
- Subjects:
- PSI -- ASDEX Upgrade -- ITER -- W divertor -- W nanostructure -- Helium
Nuclear energy -- Periodicals
Nuclear fuels -- Periodicals
Nuclear reactors -- Materials -- Periodicals
Radioactive substances -- Periodicals
621.4833 - Journal URLs:
- http://www.sciencedirect.com/science/journal/23521791 ↗
http://www.sciencedirect.com/ ↗ - DOI:
- 10.1016/j.nme.2016.11.002 ↗
- Languages:
- English
- ISSNs:
- 2352-1791
- Deposit Type:
- Legaldeposit
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- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 10734.xml