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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-PR(26)4532024
Experimental campaigns at the Joint European Torus with an ITER-like Be/W wall (JET-ILW) with pure deuterium (D), tritium (T) and Deuterium-Tritium (DT) were a unique opportunity to explore various aspects related to the ITER operation. It should also be emphasized that the JET campaign at the end of 2021 included the first tokamak experiments u…
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UKAEA-CCFE-PR(25)3202024
The development of a high current baseline scenario (I_p = 3.5MA, q95 ~3.0, beta_N < 2) in deuterium (D), tritium (T) and deuterium-tritium (D-T) for high DT fusion performance at JET with Be/W wall is described. We show that a suitable scenario capable of delivering up to 10 MW of fusion power, depending on the auxiliary heating power avail…
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UKAEA-CCFE-PR(23)1802023
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