Evaluation of tritium retention in plasma facing components during JET tritium operations

Anna Widdowson, J. Paul Coad, Yevhen Zayachuk, Ionut Jepu, Eduardo Alves, Norberto Catarino, Victoria Corregidor, Matej Mayer, Stepan Krat, Jari Likonen, Kenichiro Mizohata, Chris Rowley, Miroslaw Zlobinski, Marek Rubel, David Douai, Kalle Heinola, Tom Wauters, Laura Dittrich, Sunwoo Moon, Per PeterssonAleksandra Baron-Wiechec, Liga Avotina

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An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 × 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 × 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.
Original languageEnglish
JournalPhysica Scripta
StatePublished - 15 Dec 2021


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