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LIBRIS Formathandbok  (Information om MARC21)
FältnamnIndikatorerMetadata
00003778naa a2200613 4500
001oai:DiVA.org:kth-140091
003SwePub
008140117s2013 | |||||||||||000 ||eng|
0247 a https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-1400912 URI
0247 a https://doi.org/10.1016/j.jnucmat.2013.01.1222 DOI
040 a (SwePub)kth
041 a engb eng
042 9 SwePub
072 7a ref2 swepub-contenttype
072 7a art2 swepub-publicationtype
1001 a Brezinsek, S.4 aut
2451 0a Residual carbon content in the initial ITER-Like Wall experiments at JET
264 1b Elsevier BV,c 2013
338 a print2 rdacarrier
500 a QC 20140120
520 a The residual carbon content and carbon edge flux in JET have been assessed by three independent diagnostic techniques after start of plasma operation with the ITER-Like Wall (ILW) with beryllium first wall and tungsten divertor: (i) in-situ measurements with optical spectroscopy on low ionisation stages of carbon, (ii) charge-exchange recombination spectroscopy, and (iii) residual gas composition analysis in dedicated global gas balance experiments. Direct comparison experiments in L-mode discharges were carried out between references from the previously installed material configuration with plasma-facing components made of carbon-fibre composite (JET-CFC) and the JET-ILW. The temporal evolution of the C divertor flux since installation of the ILW has been studied in the ohmic phase of dedicated monitoring discharges which have been executed regularly throughout the experimental exploitation so far (60000 plasma seconds). The C flux behaviour in the divertor can be divided in three phases: initial fast drop, moderate reduction phase, and a long lasting phase with almost constant C flux. The Be flux in both divertor legs mirrors the behaviour of C. All experiments and diagnostic techniques demonstrate a strong reduction in C fluxes and C content of more than one order of magnitude with respect to JET-CFC which is in line with the reduction in long-term fuel retention due to co-deposition. There is no evidence of an increase in residual carbon in time, thus no indication that a damage of the thin tungsten coatings on CFC substrate in the divertor occurred.
650 7a NATURVETENSKAPx Fysikx Annan fysik0 (SwePub)103992 hsv//swe
650 7a NATURAL SCIENCESx Physical Sciencesx Other Physics Topics0 (SwePub)103992 hsv//eng
653 a Carbon-fibre composite
653 a Charge-exchange recombination spectroscopies
653 a Diagnostic techniques
653 a In-situ measurement
653 a Material configurations
653 a Optical spectroscopy
653 a Plasma-facing components
653 a Residual gas composition
653 a Electric discharges
653 a Experiments
653 a Plasmas
653 a Tokamak devices
653 a Tungsten
653 a Carbon
7001 a Jachmich, S.4 aut
7001 a Stamp, M. F.4 aut
7001 a Meigs, A. G.4 aut
7001 a Coenen, J. W.4 aut
7001 a Krieger, K.4 aut
7001 a Giroud, C.4 aut
7001 a Groth, M.4 aut
7001 a Philipps, V.4 aut
7001 a Grünhagen, S.4 aut
7001 a Smith, R.4 aut
7001 a Van Rooij, G. J.4 aut
7001 a Ivanova, Daryau KTH,Fusionsplasmafysik,Alfvénlaboratoriet,Association EURATOM-VR4 aut0 (Swepub:kth)u1c0rupi
7001 a Matthews, G. F.4 aut
7102 a KTHb Fusionsplasmafysik4 org
7730 t Journal of Nuclear Materialsd : Elsevier BVg 438:Suppl., s. S303-S308q 438:Suppl.<S303-S308x 0022-3115x 1873-4820
8564 8u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-140091
8564 8u https://doi.org/10.1016/j.jnucmat.2013.01.122

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