First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor

Corre, Y.; Chanet, Nicolas; Cotillard, R.; Gaspar, J.; Laffont, Guillaume; Pocheau, C.; Caulier, G.; Destouches, C.; Gardarein, J. L.; Firdaouss, M.; Houry, M.; Missirlian, M.; Roussel, Nicolas; Santraine, B.

doi:10.1016/j.fusengdes.2021.112528

Cited by 7 publications

(4 citation statements)

References 20 publications

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“…Focusing on the highest evolutions of both the pre-damaged and non-damaged area, for blocks located in the ISP, S a tends to increase with WEST exposure (15,16,17,18) while it tends to decrease in the OSP (25, 26, 32) (except for blocks 27 and 28 with no evolution) and for block 11, which presents a specific behavior.…”

Section: Evolution Of Surface Damage After West Exposurementioning

confidence: 97%

“…where α is the field line angle with the block surfaces (top surface, 1 mm chamfer, and poloidal leading edge), which is derived from the magnetic equilibrium and q || the heat flux density parallel to B. The parallel heat flux is computed with embedded thermal measurements [18], such as thermocouple (TC) [19] or fiber Bragg grating (FBG) optical sensors [9]. For the pulses specifically developed to maximize the heat loading on the pre-damaged blocks (I p = 500 kA, 4 MW of auxiliary power by LH during 4 s, #53947 in standard and #54067 in FISP magnetic configuration), the parallel heat fluxes computed with FBG and TC diagnostics are q || = 45 MW × m −2 and q || = 11 MW × m −2 at the OSP and ISP, respectively.…”

Section: Thermal Loading On Pre-damaged Blocksmentioning

confidence: 99%

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First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Richou¹,

Corre²,

Loewenhoff³

et al. 2022

Nucl. Fusion

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The evaluation of the impact of plasma-facing components (PFCs) damage on subsequent plasma operation is an important issue for ITER. During the first phase of operation of WEST, a few ITER like divertor plasma-facing units (PFUs) have been installed on the lower divertor. One PFU was pre-damaged under electron beam gun thermal loading, before its installation in WEST, and the subsequent evolution of the damage was studied after the WEST plasma exposure. This paper presents the procedure followed to get the pre-damaged PFU. It consists in the characterization of the response of tungsten samples representative of WEST PFU under high heat flux (HHF) loading, the selection of damage (namely small cracks, crack network, crack network and W melt droplets). Finally, according to the WEST plasma loading conditions, the blocks with damage within the PFU and the position of the pre-damaged PFU on the WEST lower divertor are attributed. The first results obtained after an initial plasma exposure in WEST lead to assess, as expected with regard to the heat loading conditions, that no major surface aspect modification was found. This result emphasized the possibility to implement as pre-damage some small local droplets of melted tungsten in a high heat loaded zone for a future WEST experimental campaign.

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Section: Evolution Of Surface Damage After West Exposurementioning

confidence: 97%

Section: Thermal Loading On Pre-damaged Blocksmentioning

confidence: 99%

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Richou¹,

Corre²,

Loewenhoff³

et al. 2022

Nucl. Fusion

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“…Due to the difficulty of the emissivity evolving during the campaign [12] this study will rely only on the embedded measurements to derive accurate energy absorbed with the components. W-coated graphite components of the LDIV are equipped with 20 embedded TCs located at 7.5 mm below the surface [10] and 4 FBGs [11] embedded at 3.5 and 7 mm below the surface, an instrumented sector with 16 TCs is shown in the figure 2(a)). The BAFF is also equipped with 8 TC embedded at 5 mm from the surface in the W-coated CuCrZr component.…”

Section: Energy Measurement From the Cooling Phase Of The Inertial Co...mentioning

confidence: 99%

“…The temperature of the inertial PFC of the LDIV and the BAFF are monitored with IR camera [9], embedded measurement by thermocouple (TC) [10] and fiber Bragg grating (FBG) [11]. Due to the difficulty of the emissivity evolving during the campaign [12] this study will rely only on the embedded measurements to derive accurate energy absorbed with the components.…”

Section: Energy Measurement From the Cooling Phase Of The Inertial Co...mentioning

confidence: 99%

Calorimetry measurement for energy balance and energy distribution in WEST for L-mode plasmas

Gaspar,

Gerardin,

Corre

et al. 2024

Nucl. Fusion

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The paper presents the energy balance of 602 pulses from four different experimental campaigns of the WEST tokamak. Different magnetic configuration has been studied with lower single null and upper single null configuration with deuterium or helium plasmas. The energy balance is closed with an imbalance of about 5% of the total injected energy for most of the campaigns and for the different magnetic configurations. The distribution over the whole machine is shown with the outer first wall receiving the most part of the energy due to its large surface area with about 30% of the total heat load, and the divertor with 25% due to the heat loads deposited by the convected power in the scrape off layer. Finally, the tomography inversion of the bolometry measurement allows to disentangle the contribution of the radiated and convected power in the energy absorbed by each type of PFC. Showing that in upper single null configuration about 63% of the available energy in the SOL is deposited in the upper divertor through convected heat loads, while in lower single null this value is spread over the lower divertor with 45% and the baffle and upper divertor with about 10% for both.

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Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES

Gaspar

Corre

Anquetin

et al. 2023

Fusion Engineering and Design

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First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor

Cited by 7 publications

References 20 publications

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

First plasma exposure of a pre-damaged ITER-like plasma-facing unit in the WEST tokamak: procedure for the PFU preparation and lessons learned

Calorimetry measurement for energy balance and energy distribution in WEST for L-mode plasmas

Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES

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