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Isotope removal experiment in JET-ILW in view of T-removal after the 2nd DT campaign at JET
KMS, ERM, Lab Plasma Phys LPP, B-1000 Brussels, Belgium..
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Fusion Plasma Physics.ORCID iD: 0000-0003-1933-8186
2022 (English)In: Physica Scripta, ISSN 0031-8949, E-ISSN 1402-4896, Vol. 97, no 4, article id 044001Article in journal (Refereed) Published
Abstract [en]

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 degrees 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 degrees C, followed by more ICWC while the vessel cooled gradually from 320 degrees C to 225 degrees 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 degrees C still removed slightly higher amounts of fuel than found previously in isotopic changeover experiments at 200 degrees 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 degrees 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.

Place, publisher, year, edition, pages
IOP Publishing , 2022. Vol. 97, no 4, article id 044001
Keywords [en]
tritium, inventory, JET, DTE2, ITER, wall conditioning
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-310192DOI: 10.1088/1402-4896/ac5856ISI: 000767895500001Scopus ID: 2-s2.0-85126681112OAI: oai:DiVA.org:kth-310192DiVA, id: diva2:1649552
Note

QC 20220404

Available from: 2022-04-04 Created: 2022-04-04 Last updated: 2022-06-25Bibliographically approved

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Dittrich, Laura

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