Investigation of tungsten alloys as plasma facing materials for the ITER divertor

Roedig, M.; Kuehnlein, Walter L.; Linke, J.; Merola, M.; Rigal, Emmanuel; Schedler, B.; Visca, E.

doi:10.1016/s0920-3796(02)00113-8

Cited by 83 publications

(39 citation statements)

References 4 publications

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“…Tiles tend to fail due to overheating [22,23] as fatigue cracks reduce the ability of the tile to conduct heat from the plasma facing surface to a visible cooling channel. From a fatigue perspective there are three scenarios which could result in failure of the tile.…”

Section: Failure Of Brazed Joints In a Plasma Facing Componentmentioning

confidence: 99%

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The challenges in predicting the fatigue life of dissimilar brazed joints and initial finite element results for a tungsten to EUROFER97 steel brazed joint

Hamilton¹,

Robbie²,

Wood³

et al. 2011

Fusion Engineering and Design

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This paper summarises the challenges in accurately predicting stress states in dissimilar brazed joints and presents initial results from a finite element analysis of a tungsten to EUROFER97 brazed joint. The residual stresses due to joint manufacture are presented and differences in stress distribution due to thermal and mechanical loading highlighted. The results from this analysis correlate well to experimental results from previous research however further validation is required. The challenges in developing fatigue assessment procedures for dissimilar brazed joints are also discussed. These fatigue assessment procedures are introduced and a validation strategy for such procedures is proposed

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Section: Failure Of Brazed Joints In a Plasma Facing Componentmentioning

confidence: 99%

“…High heat flux testing has shown [22,23] that overheating can occur due to cracking without a tile detaching. Therefore, assuming tile detachment as a failure criterion is not suitable.…”

Section: Failure Of Brazed Joints In a Plasma Facing Componentmentioning

confidence: 99%

The challenges in predicting the fatigue life of dissimilar brazed joints and initial finite element results for a tungsten to EUROFER97 steel brazed joint

Hamilton¹,

Robbie²,

Wood³

et al. 2011

Fusion Engineering and Design

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show abstract

“…The power density is calibrated most commonly by water calorimetry. 61) Power density is estimated by measuring the temperature difference between inlet and outlet coolant. The absorbed power density is calculated by the following equation,…”

Section: Non-destructive Examinationmentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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“…W has excellent thermo-mechanical properties, high thermal conductivity, low physical sputtering rate, low tritium inventory, and the highest melting point among all metals, so it is considered a promising plasma-facing material for the armors protecting the divertor of the ITER (International Thermonuclear Experimental Reactor) [1][2][3][4][5][6]. It has been already used in reactors like Joint European Torus (JET) [7] and Axially Symmetric Divertor Experiment Upgrade (ASDEX-U) [8] as a thin coating on substrates of carbon fiber composites (CFCs) and graphite.…”

Section: Introductionmentioning

confidence: 99%

Laser Pulse Effects on Plasma-Sprayed and Bulk Tungsten

Montanari

Pakhomova

Pizzoferrato

et al. 2017

Metals

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Tungsten (W) is considered a promising plasma-facing material for protecting the divertor of the ITER (International Thermonuclear Experimental Reactor). The effects on W of transient thermal loads of high energy occurring in a tokamak under operative conditions have been simulated through a single laser pulse delivered by an Nd:YAG laser. Bulk and plasma-sprayed (PS) samples have been submitted to tests and successively examined via SEM (scanning electron microscopy) observations. In both types of materials, the laser pulse induces similar effects: (i) a crater forms in the spot central area; (ii) all around the area, the ejection and the movement of molten metal give rise to a ridge; (iii) in a more external area, the surface shows plates with jagged boundaries and cracks induced by thermal stresses; (iv) the pores present in the original material become preferred ablation sites. However, the affected surface area in PS samples is larger and asymmetric if compared to that of bulk material. Such a difference has been explained by considering how microstructural characteristics influence heat propagation from the irradiated spot, and it was found that grain size and shape play a decisive role.

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Investigation of tungsten alloys as plasma facing materials for the ITER divertor

Cited by 83 publications

References 4 publications

The challenges in predicting the fatigue life of dissimilar brazed joints and initial finite element results for a tungsten to EUROFER97 steel brazed joint

The challenges in predicting the fatigue life of dissimilar brazed joints and initial finite element results for a tungsten to EUROFER97 steel brazed joint

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Laser Pulse Effects on Plasma-Sprayed and Bulk Tungsten

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