Tritium removal from JET-ILW after T and D-T experimental campaigns
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A1 Alkuperäisartikkeli tieteellisessä aikakauslehdessä
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Date
2023-11
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Language
en
Pages
15
1-15
1-15
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Nuclear Fusion, Volume 63, issue 11
Abstract
After the second Deuterium-Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium removal from wall components. The sequence started with several days of baking of the main chamber walls at 240 °C and at 320 °C. Subsequently, baking was superimposed with Ion-Cyclotron Wall Conditioning (ICWC) and Glow Discharge Conditioning (GDC) cleaning cycles in deuterium. Diverted plasma operation in deuterium with different strike point configurations, including a Raised Inner Strike Point (RISP) configuration, and with different plasma heating—Ion Cyclotron Resonance Frequency (ICRF) and Neutral Beam Injection (NBI)—concluded the cleaning sequence. Tritium content in plasma and in the pumped gas was monitored throughout the experiment. The applied fuel recovery methods allowed reducing the residual tritium content in deuterium NBI-heated plasmas to about 0.1% as deduced from neutron rate measurements. This value is well below the requirement of 1% set by the maximum 14 MeV fusion neutron budget allocated in the ensuing deuterium plasma campaign. The quantified tritium removal over the course of the experiment was 13.4 ± 0.7 × 10 22 atoms or 0.67 ± 0.03 g with ∼58% attributed to baking, ∼12.5% to ICWC, ∼26% to GDC, and ∼3.5% to first low power RISP plasmas. The experimentally estimated amount of removed tritium is in good agreement with long-term tritium accounting by the JET tritium reprocessing plant, in which the unaccounted amount was reduced by 0.71 g after the cleaning experiment.Description
Funding Information: This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No. 101052200—EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization. Publisher Copyright: © 2023 The Author(s). Published by IOP Publishing Ltd on behalf of the IAEA. All rights reserved
Keywords
DTE2, JET-ILW, tritium removal, tritium retention, wall cleaning
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Citation
Matveev, D, Douai, D, Wauters, T, Widdowson, A, Jepu, I, Maslov, M, Brezinsek, S, Dittmar, T, Monakhov, I, Jacquet, P, Dumortier, P, Sheikh, H, Felton, R, Lowry, C, Ciric, D, Banks, J, Buckingham, R, Weisen, H, Laguardia, L, Gervasini, G, de la Cal, E, Delabie, E, Ghani, Z, Gaspar, J, Romazanov, J, Groth, M, Kumpulainen, H, Karhunen, J, Knipe, S, Aleiferis, S, Loarer, T, Meigs, A, Noble, C, Papadopoulos, G, Pawelec, E, Romanelli, S, Silburn, S, Joffrin, E, Tsitrone, E, Rimini, F, Maggi, C F & JET Contributors 2023, ' Tritium removal from JET-ILW after T and D-T experimental campaigns ', Nuclear Fusion, vol. 63, no. 11, 112014, pp. 1-15 . https://doi.org/10.1088/1741-4326/acf0d4