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UKAEA-CCFE-CP(25)242025
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UKAEA-CCFE-CP(25)232025
The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was demonstrated for the first time in a tokamak operating with tritium using a remotely controlled in situ application in JET. In JET and future fusion reactors such as ITER and DEMO, thick co-deposited layers will be formed at the inner wall during exte…
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UKAEA-CCFE-CP(25)212024
Tritium inventory build-up is a safety issue for next step devices. JET brings a unique contribution on fuel retention and recovery in a metallic device, as it has operated both in deuterium (D) and deuterium-tritium (DT) plasmas. This paper will provide an overview of results from JET in this fi…
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UKAEA-CCFE-CP(24)132024
An overview of the modelling approaches, validation methods and recent main results of analysis and modelling activities related to the plasma-wall interaction in JET-ILW experiments, including the recent H/D/T campaigns is presented in the paper. Code applications to JET-ILW experiments improve general erosion/migration/retention prediction cap…
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2016
There is experimental evidence that the pedestal dynamics in type-I ELMy H-mode discharges is significantly affected by a change in the recycling conditions at the tungsten plasma-facing components (W-PFCs) after an ELM event. The integrated code JINTRAC has been employed to assess the impact of recycling conditions during type-I ELMs in JET ITER-l…
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