Overview of fuel inventory in JET with the ITER-like wall

Widdowson, A.; Coad, J. P.; Alves, E.; Baron-Wiechec, A.; Brezinsek, S.; Catarino, N.; Corregidor, V.; Heinola, K.; Koivuranta, S.; Krat, S.; Lahtinen, A.; Likonen, J.; Matthews, G. F.; Mayer, M.; Petersson, P.; Rubel, M.; Contributors, Jet

doi:10.1088/1741-4326/aa7475

Cited by 55 publications

(37 citation statements)

References 31 publications

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“…As already disclosed in a previous work [21], the origin could be local thermal desorption due to the power deposited by the ELMs. In fact, the observed D  -emission location on top of Tiles 0 and 1 coincides with the region where most D containing Beryllium co-deposits accumulate, as deduced from surface analysis studies [37,38]. If this is true, in order to generate the outgassing of trapped D, an increased power load must occur that overheats the surfaces at this region that should be correlated with the observed local increased D  -emission.…”

Section: Correlation Of Thermal Radiation To Post-elm D  -Emissionsupporting

confidence: 58%

“…Therefore alternative techniques to clean up the retained T in JET would be desirable. As already mentioned, it is known that fuel trapped in Beryllium co-deposits in the divertor can be removed by heating the surface to temperatures > 300 -350 C [37,38]. Unfortunately, such high temperatures can be reached by baking of the vacuum vessel in only marginally.…”

Section: Using Plasma Configuration To Induce Fuel Desorption From Thmentioning

confidence: 99%

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Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

Cal¹,

Losada²,

Aguilera³

et al. 2020

Plasma Phys. Control. Fusion

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It is well known since the last years that in JET, with the ITER-like wall, the performance of high-power Hmode plasmas strongly depends on the divertor magnetic topology. This is generally attributed to the effect of the magnetic field shaping on the neutral flux transport and pumping, which determine in high density H-mode plasmas the pedestal properties and finally the global confinement. In the present work we have analysed for different magnetic configurations the spatial distribution and the dynamic behaviour of the D emission. Experimental observations indicate that for certain configurations, the surface temperature and the D -emission anomalously increase on top of the inner divertor, which points to thermal outgassing there. This is the region where most Beryllium co-deposits accumulate and most Deuterium becomes trapped. The overheating at this region far from the strike point (SP) is observed to happen in magnetic configurations with reduced distance between the divertor material surface and the Separatrix (Clearance). The neutral flux that appears at the upper inner divertor during a few milliseconds after the ELM-crash, is by more than an order of magnitude larger than the puffing rate and dominates over the rest of the divertor recycling. Finally, a preliminary study describes how this thermal fuel outgassing from the co-deposited layers could be intentionally used as a Wall-conditioning technique with plasmas that focalise their particle and heat flux there. This could be used as a Wall isotope exchange technique or for Tritium recovery from regions where Be co-deposits accumulate in JET with the ITER-like wall.

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Section: Correlation Of Thermal Radiation To Post-elm D  -Emissionsupporting

confidence: 58%

Section: Using Plasma Configuration To Induce Fuel Desorption From Thmentioning

confidence: 99%

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

Cal¹,

Losada²,

Aguilera³

et al. 2020

Plasma Phys. Control. Fusion

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“…In the corner configuration the outer strike point is located on the horizontal target close to entrance to the pump duct. As reported in [48], this is a region of significant deposition, where a band of beryllium (Be) deposits has formed at the bottom of the sloping part of this tile (see Figure 18). Although visible after first campaigns with ITER-like walls in 2011-2012, the deposit was much thicker after the following campaigns in 2013-2014.…”

Section: Hot Spot On the Partly Delaminated Divertor Tilessupporting

confidence: 60%

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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“…These are hydrogen fuel isotopes (H, D, T), helium (He) originating either from the D-T fusion reaction or as fueling gas, constituents of main PFCs (C, Be, W), Fe, Cr, Ni, Mo, Nb as steel or Inconel components, elements used in plasma diagnostic systems (Mg, Al, Si) and for wall conditioning (He, Li, 9 Be, 10 B, 11 B, Si), common impurities (C, O), gases seeded for plasma edge cooling (N, Ne, Ar, Kr, Xe) and tracers for material migration introduced deliberately to the studied system in minute quantities ( 6 Li, 7 Li, 10 Be. 13 C, 15 N, 18 O, 19 F, 21 Ne, 22 Ne, Hf, Re etc. ).…”

Section: The Role Of Ion Beam Analysis For Plasma-wall Interaction Rementioning

confidence: 99%

Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges

et al. 2019

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Following the IAEA Technical Meeting on "Advanced Methodologies for the Analysis of Materials in Energy Applications Using Ion Beam Accelerators", this paper reviews the current status of ion beam analysis techniques and some aspects of ion-induced radiation damage in materials for the field of materials relevant to fusion. Available facilities, apparatus development and future research options and challenges are presented and discussed. The analysis of beryllium and radioactivity-containing samples from future experiments in JET or ITER represents not only an analytical but also a technical challenge. A comprehensive list of xxxx-xxxx/xx/xxxxxx 1

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Overview of fuel inventory in JET with the ITER-like wall

Cited by 55 publications

References 31 publications

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

Impact of divertor configuration on recycling neutral fluxes for ITER-like wall in JET H-mode plasmas

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

Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges

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