Materials R&amp;D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Stork, D.; Agostini, P.; Boutard, Jean-Louis; Buckthorpe, Derek; Diegele, E.; Dudarev, S. L.; English, C.A.; Federici, G.; Gilbert, Mark R.; Gonzalez, S.; Ibarra, Á.; Linsmeier, Ch.; Puma, A. Li; Marbach, G.; Packer, L.W.; Raj, Baldev; Rieth, M.; Tran, M.Q.; Ward, D.J.; Zinkle, S.J.

doi:10.1016/j.fusengdes.2013.11.007

Cited by 142 publications

(118 citation statements)

References 35 publications

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“…The plasma interaction temperatures are in the range of 780-3500 K causing several erosion phenomena. "The selection of plasma facing materials is mainly limited by their capability of absorbing heat and minimizing plasma contamination" [16][17][18].…”

Section: Dust In Fusion Nuclear Reactorsmentioning

confidence: 99%

“…" Figure 2 taken from [18]" shows the variation of gross erosion expected in ITER versus the distance along outer target from separatrix.…”

Section: Materials Based On Carbonmentioning

confidence: 99%

“…[18] (a) The carbon chemical erosion yield depends strongly on the target temperature, which is determined by the incident plasma power flux.…”

Section: Materials Based On Carbonmentioning

confidence: 99%

“…Calculations are done for a high and a low surface temperature case". This figure is taken from [18].…”

Section: Materials Based On Berylliummentioning

confidence: 99%

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A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

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Abstract:The choice of materials for the future nuclear fusion reactors is a crucial issue. In the fusion reactors, the combination of very high temperatures, high radiation levels, intense production of transmuting elements and high thermomechanical loads requires very high-performance materials. Erosion of PFCs (Plasma Facing Components) determines their lifetime and generates a source of impurities (i.e., in-vessel tritium and dust inventories), which cool down and dilute the plasma. The resuspension of dust could be a consequences of LOss of Coolant Accidents (LOCA) and LOss of Vacuum Accidents (LOVA) and it can be dangerous because of dust radioactivity, toxicity, and capable of causing an explosion. These characteristics can jeopardize the plant safety and pose a serious threat to the operators. The purpose of this work is to determine the experimental and numerical steeps to develop a numerical model to predict the dust resuspension consequences in case of accidents through a comparison between the experimental results taken from campaigns carried out with STARDUST-U and the numerical simulation developed with CFD codes. The authors in this work will analyze the candidate materials for the future nuclear plants and the consequences of the resuspension of its dust in case of accidents through the experience with STARDUST-U.

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Section: Dust In Fusion Nuclear Reactorsmentioning

confidence: 99%

“…" Figure 2 taken from [18]" shows the variation of gross erosion expected in ITER versus the distance along outer target from separatrix.…”

Section: Materials Based On Carbonmentioning

confidence: 99%

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A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

et al. 2016

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“…Serious risk for the divertor comes from abnormal events, such as disruptions, vertical displacement events (VDEs) and edge localized modes (ELMs). The transient loading can deposit large energies on the divertor surface (power density ~GW/m -2 ) within a period of few ms [1,2]. The transient loading might cause serious damage to the material, including structural changes such as re-crystallization (in the case of tungsten at temperatures above 1100°C), grain growth, melting, cracking, and erosion.…”

Section: Introductionmentioning

confidence: 99%

Heat load and deuterium plasma effects on SPS and WSP tungsten

et al. 2015

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Abstract. Tungsten is a prime choice for armor material in future nuclear fusion devices. For the realization of fusion, it is necessary to address issues related to the plasma-armor interactions. In this work, several types of tungsten material were studied, i.e. tungsten prepared by spark plasma sintering (SPS) and by water stabilized plasma spraying (WSP) technique. An intended surface porosity was created in the samples to model hydrogen/ helium bubbles. The samples were subjected to a laser heat loading and a radiation loading of deuterium plasma to simulate edge plasma conditions of a nuclear fusion device (power density of 10 8 W/cm 2 and 10 7 W/cm 2 , respectively, in the pulse intervals up to 200 ns). Thermally induced changes in the morphology and the damage to the studied surfaces are described. Possible consequences for the fusion device operation are pointed out.

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Materials and Processes for Fusion Reactors

AIELLO

2024

Materials and Processes for Nuclear Energy Today and in the Future

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Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Cited by 142 publications

References 35 publications

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA

Heat load and deuterium plasma effects on SPS and WSP tungsten

Materials and Processes for Fusion Reactors

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