Design and manufacturing of bulk tungsten tiles for WEST outer limiter

Firdaouss, M.; Chappuis, P.; Gazzotti, Stéphane; Lipa, M.; Portafaix, C.; Diez, M.

doi:10.1016/j.fusengdes.2020.112000

Cited by 3 publications

(2 citation statements)

References 8 publications

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“…The W coating of the outer movable bumper CFC tiles were damaged on significant areas by runaway electrons during the first plasma campaigns. The W coated CFC tiles of the outer movable bumper were replaced by bulk tungsten tiles in 2019 [13]. It is also planned, in phase 2, to replace the inner bumper tiles with bulk tungsten tiles and to implement new antenna protection limiters using the technology of the upper divertor (CuCrZr heatsink with thin tungsten coating).…”

Section: Tungsten Plasma-facing Componentsmentioning

confidence: 99%

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Bucalossi

2022

Nucl. Fusion

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WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual activities, key missions of WEST are: (i) qualification of high heat flux plasma-facing components in integrating both technological and physics aspects in relevant heat and particle exhaust conditions, particularly for the tungsten monoblocks foreseen in ITER divertor; (ii) integrated steady-state operation at high confinement, with a focus on power exhaust issues. During the phase 1 of operation (2017–2020), a set of actively cooled ITER-grade plasma facing unit prototypes was integrated into the inertially cooled W coated startup lower divertor. Up to 8.8 MW of RF power has been coupled to the plasma and divertor heat flux of up to 6 MW m−2 were reached. Long pulse operation was started, using the upper actively cooled divertor, with a discharge of about 1 min achieved. This paper gives an overview of the results achieved in phase 1. Perspectives for phase 2, operating with the full capability of the device with the complete ITER-grade actively cooled lower divertor, are also described.

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Section: Tungsten Plasma-facing Componentsmentioning

confidence: 99%

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Bucalossi

2022

Nucl. Fusion

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“…It was therefore decided to develop a new solution for the outer limiter for C4 [15] in order to better cope with runaway electrons and prepare for long pulse operation. The W-coated CFC tiles were replaced by bulk W tiles with castellated grooves to reduce eddy currents.…”

Section: Limitersmentioning

confidence: 99%

In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak

et al. 2021

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After three years of operation (2017–2019) and four experimental campaigns (C1 to C4), the first phase of operation of the WEST tokamak has now come to an end. During that period, WEST has operated with tungsten coated copper-based and carbon-based plasma facing components in order to comply with a full metallic environment. A set of components, called plasma facing units, using ITER tungsten monoblock technology was also installed onto one sector of the lower divertor to test their behaviour in a real tokamak environment. This paper gives an overview of the ageing behaviour of these components during in situ visual inspections. It is shown that tungsten coatings are in a good condition after 3 years of operation but are prone to delamination in the areas dominated by off-normal events such as runaway electrons or arcing. For this reason, the W coated carbon tiles of the outer limiter were replaced by bulk W tiles after the C3 campaign. As for the bulk tungsten ITER-like components, damage such as melting and cracking was mainly observed on the monoblock edges exposed to the parallel heat flux. The first observations show that the damage formed during C3 on the tungsten monoblocks did not evolve during C4, which leads to believe that it results from singular events rather than continuous heating due to steady state operation.

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Highly efficient porous carbons for the removal of W(VI) oxyanion from wastewaters

Dias

Don

Jandosov

et al. 2021

Journal of Hazardous Materials

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Design and manufacturing of bulk tungsten tiles for WEST outer limiter

Cited by 3 publications

References 8 publications

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak

Highly efficient porous carbons for the removal of W(VI) oxyanion from wastewaters

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