Overview of the JET ITER-like wall divertor

Widdowson, A.; Alves, E.; Baron-Wiechec, A.; Catarino, N.; Coad, J. P.; Corregidor, V.; Garcia-Carrasco, A.; Heinola, K.; Koivuranta, S.; Krat, S.; Lahtinen, A.; Likonen, J.; Mayer, M.; Petersson, P.; Rubel, M.; Boxel, Steven Van; Contributors, Jet

doi:10.1016/j.nme.2016.12.008

Cited by 51 publications

(26 citation statements)

References 15 publications

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“…Figure 6 shows the Be and C analyses on components from the inner divertor corner; the C amounts are given in italics. More pulses were run with the strike point at the inner divertor corner during ILW2 than during ILW1 [16], so more material might be expected to have travelled to the adjacent shadowed region. The only clear evidence of increased deposition, however, is the amount of deposition on the shadowed part of Tile 4.…”

Section: Results From 2014-15 Jet Operationsmentioning

confidence: 99%

“…with the surface of Tile 4 [15]. However, due to the angle of the field lines, plasma is able to reach part of the sloping region of Tile 4, and we define the plasma boundary as per the red line in figure 2, which agrees with the envelope of strike point distribution [16]. Furthermore, the sloping part of Tile 4 exposed to the plasma is in fact the strike point for many of the discharges during ILW1, so is the likely source of impurities flowing across the boundary.…”

Section: Introductionmentioning

confidence: 98%

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Impurity re-distribution in the corner regions of the JET divertor

et al. 2017

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The International Thermonuclear Experimental Reactor (ITER) will use a mixture of deuterium (D) and tritium (T) as the fuel to generate power. Since T is both radioactive and expensive the Joint European Torus (JET) has been at the forefront of research to discover how much T is used and where it may be retained within the main reaction chamber. Until the year 2010 the JET plasma facing components were constructed of carbon fibre composites (CFC). During the JET carbon (C) phases impurities accumulated at the corners of the divertor located towards the bottom of the chamber in regions shadowed from the plasma where they are very difficult to reach and remove. This build-up of C and the associated H-isotope (including T) retention were of particular concern for future fusion reactors therefore, in 2010 JET changed the wall protection to (mainly) Be and the divertor to tungsten (W)-the JET ITER-like Wall (ILW)-the choice of materials for ITER. This paper reveals that with the JET ILW impurities are still accumulating in the shadowed regions, with Be being the majority element, though the overall quantities are very much reduced from those in the C phases. The strike points for corner discharges are the principle source of the material transporting into the shadowed regions, but particles typically have about a 75% probability of reflection from lineof sight surfaces, and multiple reflection/scattering results in deposition over all surfaces.

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Section: Results From 2014-15 Jet Operationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 98%

Impurity re-distribution in the corner regions of the JET divertor

et al. 2017

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“…This is associated with tiles which did not fully undergo the prescribed heat treatment at the time of production. As is mentioned in [44] there is a known mechanism for failure of the coatings by carbidisation if surface temperatures exceed 1350°C for more than two hours [45]. However, this mechanism has not been identified in the samples analysed so far because the protection limit is below this temperature.…”

Section: Hot Spot On the Partly Delaminated Divertor Tilesmentioning

confidence: 93%

“…Delamination of tungsten coatings on a few CFC based tiles was observed after the campaigns in 2013-2014 (ILW-2) [44]. This is associated with tiles which did not fully undergo the prescribed heat treatment at the time of production.…”

Section: Hot Spot On the Partly Delaminated Divertor Tilesmentioning

confidence: 99%

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

et al. 2018

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In JET with ITER-like wall (JET-ILW), the first wall was changed to metallic materials (tungsten and beryllium) [1] which require a reliable protection system to avoid damage of the plasma-facing components (PFCs) due to beryllium melting or cracking of tungsten owing to thermal fatigue. To address this issue, a protection system with real time control, based on imaging diagnostics, has been implemented on JET-ILW in 2011.

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“…A general review on the two ILW campaigns, and on the corresponding shutdown activities are given in Refs. [9] and [10], respectively. The ILW-2 fuel retention post-mortem analyses took place after receiving samples during the JET shutdown 2015, and the first results have been published in Refs.…”

Section: Introductionmentioning

confidence: 99%

Experience on divertor fuel retention after two ITER-Like Wall campaigns

et al. 2017

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The JET ITER-Like-Wall experiment with its all-metal plasma-facing components provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during the operation of a future fusion reactor. Present work summarizes and reports the plasma fuel retention in the divertor resulting from the two first experimental campaigns with the ITER-Like Wall. The deposition pattern in the divertor after the second campaign shows same trend as was observed after the first campaign: highest deposition of 10 − 15 µm was found on top part of the inner divertor. Due to the change in plasma magnetic configurations from the first to the second campaign, and the resulted strike point locations, an increase of deposition was observed on the base of the divertor. The deuterium retention was found to be affected by the hydrogen plasma experiments done at the end of second experimental campaign.

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Overview of the JET ITER-like wall divertor

Cited by 51 publications

References 15 publications

Impurity re-distribution in the corner regions of the JET divertor

Impurity re-distribution in the corner regions of the JET divertor

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

Experience on divertor fuel retention after two ITER-Like Wall campaigns

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