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IOP Publishing, Physica Scripta, 12(96), p. 124075, 2021

DOI: 10.1088/1402-4896/ac3b30

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

This paper is made freely available by the publisher.
This paper is made freely available by the publisher.

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Abstract

Abstract 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.