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

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...

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Veröffentlicht in:Physica scripta 2021-12, Vol.96 (12), p.124075, Article 124075
Hauptverfasser: Widdowson, Anna, Coad, J Paul, Zayachuk, Yevhen, Jepu, Ionut, Alves, Eduardo, Catarino, Norberto, Corregidor, Victoria, Mayer, Matej, Krat, Stepan, Likonen, Jari, Mizohata, Kenichiro, Rowley, Chris, Zlobinski, Miroslaw, Rubel, Marek, Douai, David, Heinola, Kalle, Wauters, Tom, Dittrich, Laura, Moon, Sunwoo, Petersson, Per, Baron-Wiechec, Aleksandra, Avotina, Liga
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Sprache:eng
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Zusammenfassung: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 x 10(23) 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 x 10(22) 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.
ISSN:0031-8949
1402-4896
1402-4896
DOI:10.1088/1402-4896/ac3b30