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Deposition in the tungsten divertor during the 2011-2016 campaigns in JET with ITER-like wall

Catarino, N. (författare)
Univ Lisbon, Inst Super Tecn, IPFN, P-1049001 Lisbon, Portugal.
Widdowson, A. (författare)
Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England.
Baron-Wiechec, A. (författare)
Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England.
visa fler...
Coad, J. P. (författare)
Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England.
Heinola, K. (författare)
Univ Helsinki, POB 64, FI-00560 Helsinki, Finland.;IAEA, Div Phys & Chem Sci, Nucl Data Sect, POB 100, A-1400 Vienna, Austria.
Rubel, Marek (författare)
KTH,Fusionsplasmafysik,Assoc EURATOM VR
Barradas, N. P. (författare)
Univ Lisbon, Inst Super Tecn, IPFN, P-1049001 Lisbon, Portugal.;Univ Lisbon, Inst Super Tecn, C2TN, EN 10, P-2686953 Sacavem, Portugal.
Alves, E. (författare)
Univ Lisbon, Inst Super Tecn, IPFN, P-1049001 Lisbon, Portugal.
visa färre...
Univ Lisbon, Inst Super Tecn, IPFN, P-1049001 Lisbon, Portugal Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England. (creator_code:org_t)
2020-03-06
2020
Engelska.
Ingår i: Physica Scripta. - : IOP PUBLISHING LTD. - 0031-8949 .- 1402-4896. ; T171:1
  • Tidskriftsartikel (refereegranskat)
Abstract Ämnesord
Stäng  
  • A build-up of co-deposits in remote areas of the divertor can contribute significantly to the overall fuel retention. The control of plasma-material interactions via the study and understanding of erosion-deposition of PFCs provides vital information for the efficient future operation of ITER. The major aim of this work is to reveal details of beryllium deposition and fuel (deuterium) retention on divertor plasma-facing components removed from the JET ITER-Like Wall divertor after cumulative exposure during the first two (ILW-1+2) and all three (ILW-1+2+3) campaigns. Ion beam analysis techniques such as Rutherford backscattering spectrometry, nuclear reaction analysis and proton induced x-ray emission have been extensively used for post-mortem analyses of selected tiles from JET following each campaign and can provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. The studied divertor tiles represent a unique set of samples, which have been exposed to plasmas since the beginning of the JET-ILW operation for three successive plasma campaigns. This is a comprehensive comparison of divertor components after these operation periods. The results presented summarise deposition and fuel retention on Tiles 4 (inner base) and 6 (outer base). Although the deposition pattern is similar to that determined after individual campaigns, D retention is not a cumulative process and is determined mainly by the last campaign, and the total Be deposit after the 3 campaigns (i.e. data 1+2+3=tile exposed 2011-2016) is less than the sum of the deposits after each individual campaign (sum 1+2+3) for Tile 4 but greater for Tile 6.

Ämnesord

NATURVETENSKAP  -- Fysik (hsv//swe)
NATURAL SCIENCES  -- Physical Sciences (hsv//eng)

Nyckelord

JET
plasma-material interaction
tokamaks
ion beam analysis
deposition
tungsten
beryllium

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