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UKAEA-CCFE-CP(25)242025
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UKAEA-CCFE-PR(25)3832025
Three tungsten Langmuir probes retrieved from the JET tokamak with the ITER-Like Wall(JET-ILW) from the bulk tungsten Tile 5 have been studied. Nano-indentation, microscopy, ionbeam analysis (IBA), and X-ray diffraction were used to assess changes in their mechanicalproperties, microstructure, and phase composition. Four region…
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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)4652024
Deuterium retention was measured in beryllium samples from the JET ITER-like wall limiter tiles that were in the JET vessel for one and three campaigns (in vessel during 2015-2016 and 2011-2016, respectively), using thermal desorption spectroscopy, ion beam analysis and secondary ion mass spectrometry. It was found that overall retention increas…
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UKAEA-CCFE-CP(25)292023
INTRODUCTION Future generation tokamaks, including ITER, will strive for better confinement, which means a higher fusion plasma current to achieve a good Fusion Efficiency Factor value greater than 10 [1]. One of the major threats with this scenario is a potential for increased damage of first wall components due to unmitig…
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UKAEA-CCFE-CP(24)092023
The JET ITER-like Wall (ILW) divertor mostly consists of CFC tiles coated with a thick tungsten (W) layer over a molybdenum (Mo) interlayer. Poloidal sets of tiles are additionally coated with ~3 microns of Mo and ~4 microns of W to act as markers to measure the erosion/deposition during ILW campaigns. A few of the marker tiles only have the Mo …
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UKAEA-CCFE-CP(21)122021
This contribution outlines a strategy for assessing tritium (T) inventory in plasma facing components (PFC) during JET T operations. It is based on retention as a fraction of fuel injected in-vessel, currently reported as 0.24% for 2011-2012 operating period, in conjunction with the planned T pulse schedule providing fueling of 4 g T injected per d…
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UKAEA-CCFE-PR(21)262021
The first divertor was installed in the JET machine between 1992 and 1994 and was operated with carbon tiles and then beryllium tiles in 1994-5. Post-mortem studies after these first experiments demonstrated that most of the impurities deposited in the divertor originate in the main chamber, and that asymmetric deposition patterns generally favouri…
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UKAEA-CCFE-CP(20)1122020
Understanding of fuel retention and release processes from plasma facing components (PFCs) of ITER like wall materials is important from fundamental and technological aspects [1]. Detailed information about fuel retention and release characteristics in plasma facing components from JET will allow…
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2018
The first divertor was installed in the JET machine between 1992 and 1994 and was operated with carbon tiles and then beryllium tiles in 1994–5. Post-mortem studies after these first experiments demonstrated that most of the impurities deposited in the divertor originate in the main chamber, and that asymmetric deposition patterns generally favou…
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