Tungsten based divertor development for Wendelstein 7-X - CEA - Commissariat à l’énergie atomique et aux énergies alternatives
Article Dans Une Revue Nuclear Materials and Energy Année : 2023

Tungsten based divertor development for Wendelstein 7-X

Joris Fellinger
M. Endler
D. Naujoks
O. Schneider
M. Tekavčič

Résumé

Wendelstein 7-X, the world's largest superconducting stellarator in Greifswald (Germany), started plasma experiments with a water-cooled plasma-facing wall in 2022, allowing for long pulse operation. In parallel, a project was launched in 2021 to develop a W based divertor, replacing the current CFC divertor, to demonstrate plasma performance of a stellarator with a reactor relevant plasma facing materials with low tritium retention. The project consists of two tasks: Based on experience from the previous experimental campaigns and improved physics modelling, the geometry of the plasma-facing surface of the divertor and baffles is optimized to prevent overloads and to improve exhaust. In parallel, the manufacturing technology for a W based target module is qualified.

This paper gives a status update of project. It focusses on the conceptual design of a W based target module, the manufacturing technology and its qualification, which is conducted in the framework of the EUROfusion funded WPDIV program. A flat tile design in which a target module is made of a single target element is pursued. The technology must allow for moderate curvatures of the plasma-facing surface to follow the magnetic field lines. The target element is designed for steady state heat loads of 10 MW/m 2 (as for the CFC divertor). Target modules of a similar size and weight as for the CFC divertor are assumed (approx. < 0.25 m 2 and < 60 kg) using the existing water cooling infrastructure providing 5 l/s and roughly maximum 15 bar pressure drop per module.

The main technology under qualification is based on a CuCrZr heat sink made either by additive manufacturing using laser powder bed fusion (LPBF) or by uniaxial diffusion welding of pre-machined forged CuCrZr plates. After heat treatment, the plasma-facing side of the heat sink is covered by W or if feasible by the more ductile WNiFe, preferably by coating or alternatively by hot isostatic pressing W based tiles with a soft OFE-Cu interlayer. Last step is a final machining of the plasma-exposed surface and the interfaces to the water supply lines and supports to correct manufacturing deformations.

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Dates et versions

cea-04765092 , version 1 (04-11-2024)

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Joris Fellinger, M. Richou, G. Ehrke, M. Endler, F. Kunkel, et al.. Tungsten based divertor development for Wendelstein 7-X. Nuclear Materials and Energy, 2023, 37, pp.101506. ⟨10.1016/j.nme.2023.101506⟩. ⟨cea-04765092⟩
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