Characterization of dust collected from NSTX and JT-60U

Sharpe, John P.; Humrickhouse, Paul W.; Skinner, C.H.; Tanabe, T.; Masaki, K.; Miya, N.; Sagara, A.

doi:10.1016/j.jnucmat.2004.09.058

Cited by 47 publications

(33 citation statements)

References 3 publications

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“…Dust also can be an important contributor to impurity contamination of the core and scrape-off-layer ͑SOL͒ plasmas in tokamak fusion devices, [1][2][3][4] which may increase radiation loss from the plasmas and affect recycling regimes in the divertor regions. Thus, novel experimental and theoretical studies [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19] on dust composition; mechanisms of dust formation; dust thermochemical, electrical, magnetic and radiative properties; statistical distribution of dust particles over sizes, shapes, porosity, etc. ; and dust transport in fusion plasma devices have started.…”

Section: Introductionmentioning

confidence: 99%

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Modeling of dust-particle behavior for different materials in plasmas

et al. 2007

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The behavior of dust particles made of different fusion-related materials ͑Li, Be, B, C, Fe, Mo, or W͒ in tokamak plasmas is simulated using the dust transport code DUSTT ͓A. Pigarov et al., Phys. Plasmas 12, 122508 ͑2005͔͒. The dependencies of the characteristic lifetime of dust particles on plasma parameters are compared for the different dust materials. The dynamics of dust particles in the tokamak edge plasma is studied and the effects of dust material on the acceleration, heating, and evaporation/sublimation of particles are analyzed.

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Section: Introductionmentioning

confidence: 99%

“…Note that boron was widely used in recent fusion plasma experiments as the restorable coating of PFCs. All these elements are found to form the dust particles collected and analyzed from the interiors of tokamaks 16 and stellarators. 17 Lithium is considered as one of basic materials in the liquid first wall concept.…”

Section: Introductionmentioning

confidence: 99%

Modeling of dust-particle behavior for different materials in plasmas

et al. 2007

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“…[5][6][7][8][9][10][11]), dust particles of 10 nm -100 µm in size are unavoidably present in all fusion devices (as well as larger flakes and loose co-deposited layers of a millimeter and more). Routine analysis [6][7][8][9][10] of dust collected after the vent-to-air in many tokamaks and stellarators give insight into dust distributions, characteristics, and total mass. This analysis indicates that dust particles are comprised mainly of the plasma facing component (PFC) materials used in these machines.…”

Section: Introductionmentioning

confidence: 99%

“…This analysis indicates that dust particles are comprised mainly of the plasma facing component (PFC) materials used in these machines. These particles had irregular shape akin to grains or globules, and the maximal and minimal dimensions of individual particles do not differ substantially [6,7]. Some characteristics of dust collected in DIII-D, Alcator C-Mod, and NSTX tokamaks are given in Table 1.…”

Section: Introductionmentioning

confidence: 99%

Dust-particle transport in tokamak edge plasmas

Pigarov

Krasheninnikov

Soboleva³

et al. 2005

Physics of Plasmas

140

120

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Dust particulates in the size range of 10nm-100µm are found in all fusion devices. Such dust can be generated during tokamak operation due to strong plasma/material-surface interactions. Some recent experiments and theoretical estimates indicate that dust particles can provide an important source of impurities in the tokamak plasma. Moreover, dust can be a serious threat to the safety of next-step fusion devices. In this paper, recent experimental observations on dust in fusion devices are reviewed. A physical model for dust transport simulation, and a newly developed code DUSTT, are discussed. The DUSTT code incorporates both dust dynamics due to comprehensive dust-plasma interactions as well as the effects of dust heating, charging, and evaporation. The code tracks test dust particles in realistic plasma backgrounds as provided by edge-plasma transport codes. Results are presented for dust transport in current and next-step tokamaks. The effect of dust on divertor plasma profiles and core plasma contamination is examined.3

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“…The activity and density of dust are estimated from the administrative limits in the ITER preliminary safety report [2]. Dust size is estimated from an existing experimental fusion machine with a count median diameter of 1.32 -14.39 µm [4,5].…”

Section: Dust Specificationsmentioning

confidence: 99%

Dust Removal Experiments for ITER Blanket Remote Handling System

Ueno

Aburadani

Saito

et al. 2014

Plasma and Fusion Research

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To reduce maintenance workers' dose rate caused by activated dust adhering to the ITER blanket remote handling system (BRHS), dust must be removed from BRHS surfaces. Dust that adheres to the top surface of the BRHS rail from cyclic loading of the vehicle manipulator is considered to be the most difficult dust to remove. Dust removal experiments were conducted to simulate the materials, conditions, and cyclic loading of actual BRHS operations. The tungsten powder used to simulate the dust was squashed, and the area of contact by cyclic load was increased, but the powder was not embedded into the matrix. The increase in the area of contact increased the total intermolecular force between a tungsten particle and the surface, which was considered the main force adhering dust to the test piece surface. A combination of dust removal methods, including vacuum cleaning and brushing, was applied to the simulated dust that adhered to the test pieces. The results showed that vacuum cleaning is effective in removing dust from the non-cyclic loaded surface. The combined methods were highly efficient in removing the dust that strongly adhered to the rail surface.

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Characterization of dust collected from NSTX and JT-60U

Cited by 47 publications

References 3 publications

Modeling of dust-particle behavior for different materials in plasmas

Modeling of dust-particle behavior for different materials in plasmas

Dust-particle transport in tokamak edge plasmas

Dust Removal Experiments for ITER Blanket Remote Handling System

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