Isotope removal experiment in JET-ILW in view of T-removal after the 2nd DT campaign at JET

Autor: T Wauters, D Matveev, D Douai, J Banks, R Buckingham, I S Carvalho, E de la Cal, E Delabie, T Dittmar, J Gaspar, A Huber, I Jepu, J Karhunen, S Knipe, M Maslov, A Meigs, I Monakhov, V S Neverov, C Noble, G Papadopoulos, E Pawelec, S Romanelli, A Shaw, H Sheikh, S Silburn, A Widdowson, P Abreu, S Aleiferis, J Bernardo, D Borodin, S Brezinsek, J Buermans, P Card, P Carvalho, K Crombe, S Dalley, L Dittrich, C Elsmore, M Groth, S Hacquin, R Henriques, V Huber, P Jacquet, X Jiang, G Jones, D Keeling, D Kinna, K Kirov, M Kovari, E Kowalska-Strzeciwilk, A B Kukushkin, H Kumpulainen, E Litherland-Smith, P Lomas, T Loarer, C Lowry, A Manzanares, A Patel, A Peacock, P Petersson, N Petrella, R A Pitts, J Romazanov, M Rubel, P Siren, T Smart, E R Solano, Ž Štancar, J Varje, A Whitehead, S Wiesen, M Zerbini, M Zlobinski
Přispěvatelé: Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), Royal Military Academy, Forschungszentrum Jülich, CEA, Culham Science Centre, Universidade Lisboa, CIEMAT, Oak Ridge National Laboratory, Aix-Marseille Université, National Institute for Laser, Plasma and Radiation Physics, University of Helsinki, Russian Research Centre Kurchatov Institute, University of Opole, Demokritos National Centre for Scientific Research, KTH Royal Institute of Technology, Fusion and Plasma Physics, Department of Applied Physics, Complutense University, Aalto-yliopisto, Aalto University
Jazyk: angličtina
Rok vydání: 2022
Předmět:
Zdroj: Physica scripta 97(4), 044001-(2022). doi:10.1088/1402-4896/ac5856
Physica Scripta
Physica Scripta, 2022, 97 (4), pp.044001. ⟨10.1088/1402-4896/ac5856⟩
ISSN: 0031-8949
1402-4896
DOI: 10.1088/1402-4896/ac5856
Popis: A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce the plasma deuterium concentration to less than 1% in preparation for operation with tritium. This was also a key activity with regard to refining the clean-up strategy to be implemented at the end of the 2nd DT campaign in JET (DTE2) and to assess the tools that are envisaged to mitigate the tritium inventory build-up in ITER. The sequence began with 4 days of main chamber baking at 320 °C, followed by a further 4 days in which Ion Cyclotron Wall Conditioning (ICWC) and Glow Discharge Conditioning (GDC) were applied with hydrogen fuelling, still at 320 °C, followed by more ICWC while the vessel cooled gradually from 320 °C to 225 °C on the 4th day. While baking alone is very efficient at recovering fuel from the main chamber, the ICWC and GDC sessions at 320 °C still removed slightly higher amounts of fuel than found previously in isotopic changeover experiments at 200 °C in JET. Finally, GDC and ICWC are found to have similar removal efficiency per unit of discharge energy. The baking week with ICWC and GDC was followed by plasma discharges to remove deposited fuel from the divertor. Raising the inner divertor strike point up to the uppermost accessible point allowed local heating of the surfaces to at least 800 °C for the duration of this discharge configuration (typically 18 s), according to infra-red thermography measurements. In laboratory thermal desorption measurements, maintaining this temperature level for several minutes depletes thick co-deposit samples of fuel. The fuel removal by 14 diverted plasma discharges is analysed, of which 9, for 160 s in total, with raised inner strike point. The initial D content in these discharges started at the low value of 3%–5%, due to the preceding baking and conditioning sequence, and reduced further to 1%, depending on the applied configuration, thus meeting the experimental target.
Databáze: OpenAIRE
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