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Comparison of the structure of the plasma-facing surface and tritium accumulation in beryllium tiles from JET ILW campaigns 2011-2012 and 2013-2014

JET Contributors; Pajuste, Elina; Kizane, Gunta; Igaune, Ieva; Avotina, Liga; Litaudon, X.; Abduallev, S.; Abhangi, M.; Abreu, P.; Afzal, M.; Aggarwal, K. M.; Ahlgren, T.; Ahn, J. H.; Aho-Mantila, L.; Aiba, N.; Airila, M.; Albanese, R.; Aldred, V.; Alegre, D.; Alessi, E.; Aleynikov, P.; ... mehr

Abstract:
In this study, beryllium tiles from Joint European Torus (JET) vacuum vessel wall were analysed and compared regarding their position in the vacuum vessel and differences in the exploitation conditions during two campaigns of ITER-Like-Wall (ILW) in 2011–2012 (ILW1) and 2013–2014 (ILW2) Tritium content in beryllium samples were assessed. Two methods were used to measure tritium content in the samples – dissolution under controlled conditions and tritium thermal desorption. Prior to desorption and dissolution experiments, scanning electron microscopy and energy dispersive x-ray spectroscopy were used to study structure and chemical composition of plasma-facing-surfaces of the beryllium samples. Experimental results revealed that tritium content in the samples is in range of 2·10$^{11}$–2·10$^{13}$ tritium atoms per square centimetre of the surface area with its highest content in the samples from the outer wall of the vacuum vessel (up to 1.9·10$^{13}$ atoms/cm$^{2}$ in ILW1 campaign and 2.4·10$^{13}$ atoms/cm$^{2}$ in ILW2). The lowest content of tritium was found in the upper part of the vacuum vessel (2.0·10$^{12}$ atoms/cm$^{2}$ and 2.0·10$^{11}$ atoms/cm$^{2}$ in ILW1 and ILW2, respectively).
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Verlagsausgabe §
DOI: 10.5445/IR/1000119796
Veröffentlicht am 27.05.2020
Originalveröffentlichung
DOI: 10.1016/j.nme.2019.02.011
Scopus
Zitationen: 6
Web of Science
Zitationen: 4
Dimensions
Zitationen: 5
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Thermofluidik (IATF)
Institut für Technische Physik (ITEP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 05.2019
Sprache Englisch
Identifikator ISSN: 2352-1791
KITopen-ID: 1000119796
Erschienen in Nuclear materials and energy
Verlag Elsevier
Band 19
Seiten 131-136
Schlagwörter Tritium, Beryllium, ITER-like wall, Joint European Torus, Fuel retention
Nachgewiesen in Dimensions
Web of Science
Scopus
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