Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns

Diez, M.; Balden, M.; Bresinzek, S.; Corre, Y.; Fedorczak, N.; Firdaouss, M.; Fortuna, E.; Gaspar, J.; Gunn, J.; Hakola, A.; Loarer, T.; Martin, Céline; Mayer, M.; Reilhac, P. Roux de; Richou, M.; Tsitrone, E.; Vuoriheimo, Tomi

doi:10.1016/j.nme.2023.101399

Cited by 5 publications

(3 citation statements)

References 28 publications

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“…They are then assembled to obtain the 12 sectors which finally pave the lower divertor of WEST. The studied monoblock is referenced MB4 and belongs to the PFU named ILP7 (7th ITER-like PFU, see the overview of Diez et al [18]). The MB4 monoblock is located 100 mm from the inner end of the PFU (high field side).…”

Section: Analyzed Targetmentioning

confidence: 99%

“…The MB4 monoblock is located 100 mm from the inner end of the PFU (high field side). This MB4 monoblock was in WEST between 2017 and 2019 during four plasma operations and has been exposed to H, D, He and metallic species of different origins [18]. These species include Ag (due to a probe erosion and antennas coating), B (due to the machine boronization), C (due to the erosion of the former limiter and of the graphite substrate of the coated PFUs used in the phase1 of WEST), Cu, Mo (used as interlayer between the CFC substrate and the W coating on the lower divertor tiles), Ni, O and W (due to the divertor erosion and W environment of WEST).…”

Section: Analyzed Targetmentioning

confidence: 99%

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A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak

Favre,

Bultel,

Lamine Sankhe

et al. 2024

Phys. Scr.

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As part of the development of proven diagnostics allowing the characterization of ITER’s PFUs (Plasma Facing Units) without dismantling, LIBS (Laser-Induced Breakdown Spectroscopy) is a serious candidate for determining the multi-elemental composition. In this article, we report a measurement campaign carried out within the WEST tokamak using an original device based on the following technological choices. (1) The laser source and the spectrometer are placed outside the tokamak. (2) The laser pulses are conveyed by an optical fiber. (3) The signals are collected by a second optical fiber. (4) The optical focusing and collection device is placed in the desired location by a remote handling arm (AIA, Articulated Inspection Arm). The processed signals allow the measurement of the composition of the irradiated material. The technological choices are discussed in the light of their implementation and proposals are made for a more efficient future version of the system.

show abstract

Section: Analyzed Targetmentioning

confidence: 99%

Section: Analyzed Targetmentioning

confidence: 99%

A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak

Favre,

Bultel,

Lamine Sankhe

et al. 2024

Phys. Scr.

View full text Add to dashboard Cite

show abstract

“…As a result of particular instabilities, the plasma will interact with the inner vacuum vessel walls and encourage the production of other structures, such as dust, fuzz, etc. These structures can be redeposited on the divertor's surface, leading to significant contamination of the divertor region or other PFCs (plasma facing components) [1][2][3][4][5]. Furthermore, dust may retain a sizable amount of tritium gas depending on its shape.…”

Section: Introductionmentioning

confidence: 99%

Tungsten Material Behavior under H2, D2, and He Plasma Interaction Conditions in the Framework of Fusion-Relevant Studies

Stancu,

Marascu,

Bonciu

et al. 2023

Materials

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In the current study, bulk tungsten material surfaces are exposed to hydrogen, deuterium, and helium plasmas in the radiofrequency domain (13.56 MHz) at an input power of 250 W using the hollow-cathode configuration. The ejected material is collected on titanium substrates at various distances (from 6 mm up to 40 mm). Therefore, the exposed tungsten materials are investigated for surface changes (blister occurrence, dust formation, or nano-structuration), along with the crystallinity, depending on the plasma’s exposure times (from 30 min up to 120 min for each plasma type). Also, the collected materials are analyzed (morphological, structural, and statistical investigations) for dust and dust film-like appearance. Plasma discharges are analyzed using two methods: optical emission spectroscopy, and single Langmuir probes, to emphasize the nature of the used plasmas (cold discharges, ~2 eV), along with the presence of tungsten emission (e.g., WI 406.31 nm, WI 421.31 nm) during the plasma lifetime. By using a dedicated protocol, a method was established for obtaining fusion-relevant tungsten surfaces in the hydrogen and deuterium plasma discharges. By using the implemented method, the current paper introduces the possibility of obtaining a new tungsten morphology, i.e., the dandelion-like shape, by using helium plasma, in which the W18O49 compound can be found.

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Calculation of in-situ steady-state heat flux on EAST lower divertor

He,

Zhu,

Wang

et al. 2024

Nuclear Materials and Energy

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Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns

Cited by 5 publications

References 28 publications

A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak

A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak

Tungsten Material Behavior under H2, D2, and He Plasma Interaction Conditions in the Framework of Fusion-Relevant Studies

Calculation of in-situ steady-state heat flux on EAST lower divertor

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