Development and qualification of a bulk tungsten divertor row for JET

Ph Mertens; H. Altmann; T. Hirai; V. Philipps; G. Pintsuk; J. Rapp; V. Riccardo; B. Schweer; I. Uytdenhouwen; U. Samm

doi:10.1016/j.jnucmat.2009.01.253

Development and qualification of a bulk tungsten divertor row for JET

Ph Mertens, H. Altmann, T. Hirai, V. Philipps, G. Pintsuk, J. Rapp, V. Riccardo, B. Schweer, I. Uytdenhouwen, U. Samm

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23 Scopus citations

Abstract

A bulk tungsten divertor row has been developed in the frame of the ITER-like Wall project at JET. It consists of 96 tiles grouped in 48 modules around the torus. The outer strike point is located on those tiles for most of the ITER-relevant, high triangularity plasmas. High power loads (locally up to 10-20 MW/m²) and erosion rates are expected, even a risk of melting, especially with the transients or ELM loads. These are demanding conditions for an inertially cooled design as prescribed. A lamella design has been selected for the tungsten, arranged to control the eddy and halo current flows. The lamellae must also withstand high temperature gradients (2200 to 220 °C over 40 mm height), without overheating the supporting carrier (600-700 °C maximum). As a consequence of the tungsten emissivity, the radiative cooling drops appreciably in comparison with the current CFC tiles, calling for interleaved plasma scenarios in terms of performance. The compromise between shadowing and power handling is discussed, as well as the consequences for operation. Prototypes have been exposed in TEXTOR and in an electron beam facility (JUDITH-2) to the nominal power density of 7 MW/m² for 10 s and, in addition, to higher loads leading to surface temperatures above 2000 °C.

Original language	English
Pages (from-to)	967-970
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	390-391
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2009.01.253
State	Published - Jun 15 2009
Externally published	Yes

Funding

This work, supported by the European Communities under the contract of Association between EURATOM and Forschungszentrum Jülich, was carried out within the framework of the European Fusion Development Agreement (EFDA). The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Funders	Funder number
H2020 Euratom
Engineering and Physical Sciences Research Council	EP/G003955/1
Forschungszentrum Jülich

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.jnucmat.2009.01.253

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abstract = "A bulk tungsten divertor row has been developed in the frame of the ITER-like Wall project at JET. It consists of 96 tiles grouped in 48 modules around the torus. The outer strike point is located on those tiles for most of the ITER-relevant, high triangularity plasmas. High power loads (locally up to 10-20 MW/m2) and erosion rates are expected, even a risk of melting, especially with the transients or ELM loads. These are demanding conditions for an inertially cooled design as prescribed. A lamella design has been selected for the tungsten, arranged to control the eddy and halo current flows. The lamellae must also withstand high temperature gradients (2200 to 220 °C over 40 mm height), without overheating the supporting carrier (600-700 °C maximum). As a consequence of the tungsten emissivity, the radiative cooling drops appreciably in comparison with the current CFC tiles, calling for interleaved plasma scenarios in terms of performance. The compromise between shadowing and power handling is discussed, as well as the consequences for operation. Prototypes have been exposed in TEXTOR and in an electron beam facility (JUDITH-2) to the nominal power density of 7 MW/m2 for 10 s and, in addition, to higher loads leading to surface temperatures above 2000 °C.",

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AU - Rapp, J.

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AU - Schweer, B.

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AU - Samm, U.

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Development and qualification of a bulk tungsten divertor row for JET

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