3D finite element electromagnetic and stress analyses of the JET LB-SRP divertor element (tungsten lamella design)

“…In comparison to the pure elastic calculation in ref. [12], the main stress in the upper part of the lamella (0-13 mm depth) has dropped from 150 MPa to about 120 MPa owing to the introduction of plasticity. Of course, incursion into the plastic domain is determined by the actual yield stress which is very much temperature dependent (Fig.2).…”

Section: Results Of Thermal Cyclingmentioning

confidence: 99%

Bulk tungsten in the JET divertor: Potential influence of the exhaustion of ductility and grain growth on the lifetime

Mertens¹,

Thompson²,

Matthews³

et al. 2013

Journal of Nuclear Materials

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“…The design was mostly determined by the strong constraint of minimising electromagnetic forces during disruptions and optimising mechanical stability [16,17]. A design was made of 6 mm W lamellae, packed together in four poloidal stacks and bolted together in toroidal direction but with electrical isolating spacers to reduce eddy currents [15].…”

Section: Tungsten Divertor/randd On Tungsten Coating and Bulk Tungsten mentioning

confidence: 99%

The JET programme in support of ITER

Paméla¹,

Romanelli

Watkins

et al. 2007

Fusion Engineering and Design

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The mid-term experimental programme of the JET tokamak exploits its recently enhanced scientific capabilities (e.g., new divertor allowing high-triangularity ITER-relevant scenarios, several new diagnostics) to address critical issues potentially impacting the detailed design of ITER components (e.g., first wall, heating and current drive systems, diagnostics) and, in parallel, further develop ITER-operating scenarios and address specific physics issues of direct relevance to ITER (e.g., transport physics, burning plasma physics). For the longer term, activities on a "JET programme in support of ITER" have been launched, aiming at making optimal use of JET's unique features: large plasma size and capability to handle beryllium and tritium. A full replacement of the first wall materials is planned (beryllium in the main wall and tungsten in the divertor). This should deliver answers to urgent plasma surface interaction questions, such as tritium retention, and provide operational experience in steady and transient conditions with ITER wall materials under relevant geometry and relevant plasma conditions. In addition, the JET auxiliary heating power will be upgraded to ∼45 MW, allowing access to ITER-relevant disruption and edge localised modes energy loss densities. This will open access to conditions of melt layer formation both on the beryllium first wall and the * Corresponding author at: EFDA-JET, J. Paméla et al. / Fusion Engineering and Design 82 (2007) 590-602 591 tungsten divertor and, on the other hand, help progressing, in particular, hybrid and advanced scenarios for ITER, which require full or partial current profile control, thereby making use of new dedicated diagnostics.

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3D finite element electromagnetic and stress analyses of the JET LB-SRP divertor element (tungsten lamella design)

Cited by 11 publications

References 7 publications

A bulk tungsten divertor row for the outer strike point in JET

A bulk tungsten divertor row for the outer strike point in JET

Bulk tungsten in the JET divertor: Potential influence of the exhaustion of ductility and grain growth on the lifetime

The JET programme in support of ITER

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