Publication: Evaluation of tritium retention in plasma facing components during JET tritium operations
Дата
2021
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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 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.
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Evaluation of tritium retention in plasma facing components during JET tritium operations / Widdowson, A [et al.] // Physica Scripta. - 2021. - 96. - № 12. - 10.1088/1402-4896/ac3b30
URI
https://www.doi.org/10.1088/1402-4896/ac3b30
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https://openrepository.mephi.ru/handle/123456789/25130
https://www.scopus.com/record/display.uri?eid=2-s2.0-85123217523&origin=resultslist
http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000730651000001
https://openrepository.mephi.ru/handle/123456789/25130