Publication | Open Access
Evaluation of tritium retention in plasma facing components during JET tritium operations
38
Citations
28
References
2021
Year
Jet Dt OperationsEngineeringPlasma Facing ComponentsControlled Nuclear FusionFusion PowerInertial Confinement FusionTritium RetentionJet TPlasma PhysicsNuclear MaterialsJet Tritium OperationsPlasma ApplicationMagnetic Confinement FusionFusion Reactor MaterialPlasma ProcessingNuclear Astrophysics
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 × 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 × 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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