Dust mobilization experiments in the context of the fusion plants—STARDUST facility

Porfiri, M; Forgione, Nicola; Paci, Sandro; Rufoloni, A.

doi:10.1016/j.fusengdes.2005.07.034

Cited by 24 publications

(20 citation statements)

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“…The dust mean diameters measured were 0.3-0.5 µm for W, 20-30 µm for SS316 and 4-5 µm for C. The dust size distributions are shown in figure 5 for C (received from FZK), in figure 6 for W (treated by carbon deposition, 2.0-3.0 nm) and in figure 7 for SS316 (treated by carbon deposition, 2.0-3.0 nm). The results of the SEM scanning revealed a size distribution of the dust different from those declared by the commercial companies, that were 0.6-0.9 µm for W and 45 µm for SS316 against the 0.3-0.5 µm detected by the SEM for W and 15-30 µm for SS316, respectively [7].…”

Section: New Stardust Experimental Setupmentioning

confidence: 84%

“…The type of dust used (W, C, SS316) is similar to that found inside the vacuum chamber of a fusion facility, when the plasma facing materials vaporize for high energy deposition due to the disruptions [7]. Scanning electron microscope (SEM) analysis has been carried out for characterizing the commercial dust used for the experiments [7].…”

Section: New Stardust Experimental Setupmentioning

confidence: 99%

“…Among the dust sizes commercially available, those similar to the dusts generated in the disruption phenomena have been chosen [7]. While the W and the C grains had the tendency to agglomerate with each other, the stainless steel, being of bigger size and with a high specific weight, remained well separated.…”

Section: New Stardust Experimental Setupmentioning

confidence: 99%

“…• C) of 6 kg each of C, Be and W [2]. These administrative limits have been fixed to avoid, also in the case of severe accident, the evacuation of the population from the area surrounding the plant [2] because the consequent calculated releases should cause doses below the limits according to the current recommendations of the International Commission on Radiological Protection.…”

Section: Introductionmentioning

confidence: 99%

“…For validation purposes, the CFD simulation data were extracted at the same locations where the experimental data were collected. The implemented fluid-dynamic model is based on the fully compressible formulation of the continuity equation (2) and the momentum equation (3) (gravity effects are included):…”

Section: Introductionmentioning

confidence: 99%

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STARDUST experimental campaign and numerical simulations: influence of obstacles and temperature on dust resuspension in a vacuum vessel under LOVA

et al. 2011

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Activated dust mobilization during a Loss of Vacuum Accident (LOVA) is one of the safety concerns for the International Thermonuclear Experimental Reactor (ITER). Intense thermal loads in fusion devices occur during plasma disruptions, edge localized modes and vertical displacement events. They will result in macroscopic erosion of the plasma facing materials and consequent accumulation of activated dust into the ITER vacuum vessel (VV). These kinds of events can cause dust leakage outside the VV that represents a high radiological risk for the workers and the population. A small facility, Small Tank for Aerosol Removal and Dust (STARDUST), was set up at the ENEA Frascati laboratories to perform experiments concerning the dust mobilization in a volume with the initial conditions similar to those existing in ITER VV. The aim of this work was to reproduce a low pressurization rate (300 Pa s −1 ) LOVA event in a VV due to a small air leakage for two different positions of the leak, at the equatorial port level and at the divertor port level, in order to evaluate the influence of obstacles and walls temperature on dust resuspension during both maintenance (MC) and accident conditions (AC) (T walls = 25• C MC, 110• C AC). The dusts used were tungsten (W), stainless steel 316 (SS316) and carbon (C), similar to those produced inside the vacuum chamber in a fusion reactor when the plasma facing materials vaporize due to the high energy deposition. The experimental campaign has been carried out by introducing inside STARDUST facility an obstacle to simulate the presence of objects, such as divertor. In the obstacle a slit was cut to simulate the limiter-divertor gap inside ITER VV. In this paper experimental campaign results are shown in order to investigate how the divertor and limiterdivertor gap influence dust mobilization into a VV. A two-dimensional (2D) modelling of STARDUST was made using the CFD commercial code FLUENT, in order to get a preliminary overview of the fluid dynamics behaviour during a LOVA event and to justify the mobilization data. In addition, a numerical model was developed to compare numerical results with experimental ones.

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Section: New Stardust Experimental Setupmentioning

confidence: 84%

Section: New Stardust Experimental Setupmentioning

confidence: 99%

Section: New Stardust Experimental Setupmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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STARDUST experimental campaign and numerical simulations: influence of obstacles and temperature on dust resuspension in a vacuum vessel under LOVA

et al. 2011

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Plasma‐material Interactions Problems and Dust Creation and Re‐suspension in Case of Accidents in Nuclear Fusion Plants: A New Challenge for Reactors like ITER and DEMO

Malizia

Poggi

Ciparisse

et al. 2016

Advanced Surface Engineering Materials

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Given the urgent need to converge on precise guidelines for accident management\ud in nuclear fusion plants, in this paper, the authors will analyze the problem\ud related to the choice of possible candidate materials for the nuclear fusion plants\ud like International Thermonuclear Experimental Reactor (ITER), DEMOnstration\ud power plant (DEMO), or PROTOtype power plant (PROTO). Fusion power is\ud a promising long-term candidate to supply the energy needs of humanity. From\ud the safety point of view, nuclear fusion holds inherent and potential safety advantages\ud over other energy sources. In magnetic confinement devices, the plasma\ud edge and surrounding material surfaces provide a buffer zone between the hightemperature\ud conditions in the plasma core and the normal “terrestrial” environment.\ud The interaction between the plasma edge and the surrounding surfaces\ud profoundly influences the conditions in the plasma core and is the principal key\ud engineering issue. Robust solutions to plasma–material interactions (PMIs) issues\ud are required to realize a commercially attractive fusion reactor. PMIs critically\ud affect tokamak operation in many ways. Erosion by the plasma determines the\ud lifetime of plasma-facing components (PFCs) and generates a source of impurities,which cool and dilute the plasma. Deposition of material onto PFCs alters their\ud surface composition and can lead to long-term accumulation of large in-vessel\ud tritium inventories. Retention and recycling of hydrogen from PFCs affect fueling\ud efficiency, plasma density control, and the density of neutral hydrogen in the\ud plasma boundary, which impacts particle and energy transport. Dusts are currently\ud produced in the existing plants like JET (and will also be in the future ones\ud like ITER, DEMO, and PROTO) by PMIs. Thus, the issues related to the PFCs of\ud the first wall of the nuclear fusion plants area topic that the Quantum Electronics\ud and Plasma Physics Research Group have been studying for more than a decade.\ud Regarding the selection of PFCs, there are two strong school of thoughts that\ud work on fusion plants materials for the first wall: (1) one composed by experts\ud working mainly on nuclear fusion and that are focusing their attention on certain\ud materials (like tungsten, beryllium, carbon, tritium, stainless steel, and other),\ud and (2) the other one composed of experts working mainly on the fission plants\ud that want to demonstrate the “dual-use” characteristics of the “fission materials”\ud for fusion plants applications. In this review paper, the authors will (1) review\ud both the approaches mentioned above comparing the main characteristics of all\ud the proposed and tested materials, (2) analyze the consequences (experimentally\ud revealed and numerically predicted) of PMIs that provokes serious damages to the\ud plants and dangerous consequences like radioactive/toxic dust production, and\ud (3) analyze (also thanks to our experimental activities on STARDUST-Upgrade\ud facility) the risks (for th...

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Numerical Study on the Flow and Heat Transfer Characteristics in CFETR Cryostat During a Loss of Vacuum

Huang,

Wei,

et al. 2023

Proceedings of the 28th International Cryogenic Engineering Conference and International Cryogenic Materials Conference 2022

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Dust mobilization experiments in the context of the fusion plants—STARDUST facility

Cited by 24 publications

References 1 publication

STARDUST experimental campaign and numerical simulations: influence of obstacles and temperature on dust resuspension in a vacuum vessel under LOVA

STARDUST experimental campaign and numerical simulations: influence of obstacles and temperature on dust resuspension in a vacuum vessel under LOVA

Plasma‐material Interactions Problems and Dust Creation and Re‐suspension in Case of Accidents in Nuclear Fusion Plants: A New Challenge for Reactors like ITER and DEMO

Numerical Study on the Flow and Heat Transfer Characteristics in CFETR Cryostat During a Loss of Vacuum

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