First wall and divertor plate sputtering in a tokamak reactor

Абрамов, В. А.; Igitkhanov, Yu.; Pistunovich, V.I.; Pozharov, V.A.

doi:10.1016/0022-3115(89)90313-9

Cited by 23 publications

(14 citation statements)

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“…7b for divertor all-W plate. Stronger erosion of divertor plates compared with the FW erosion is due to the acceleration of incoming ions in the sheath potential and strong deviation of energy distribution function from Maxwellian [11]. It is seen that at temperatures ≤100 eV sputtering of W material is negligible.…”

Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 89%

“…the FW blanket armour, limiter, etc.) sputtered during t operation time by incident particle fluxes j of different species j, can be expressed as [11] …”

Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 99%

“…Here we present the results of erosion rate calculation taking into account deviation the distribution function at the divertor plates from Maxwellian due to the sheath acceleration and the angular dependence of the sputtering yield. Following [11] the twice averaged sputtering yield, defined as the yield averaged over the distribution of energy and angle of incidence of the projectiles, is given by…”

Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 99%

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Evaluation of energy and particle impact on the plasma facing components in DEMO

Igitkhanov

Базылев

2012

Fusion Engineering and Design

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Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 89%

“…the FW blanket armour, limiter, etc.) sputtered during t operation time by incident particle fluxes j of different species j, can be expressed as [11] …”

Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 99%

Section: Sputter Erosion In a Long-range Operationmentioning

confidence: 99%

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Evaluation of energy and particle impact on the plasma facing components in DEMO

Igitkhanov

Базылев

2012

Fusion Engineering and Design

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“…For the background plasma an averaged yield over distribution of energy and angle of incidence particles is calculated according to [15].…”

Section: Plasma Surface Interactionmentioning

confidence: 99%

Impurity Transport Modelling in Edge Plasmas of Fusion Devices with the Monte Carlo Code ERO

Droste¹,

Borodin²,

Kirschner³

et al. 2006

Contrib. Plasma Phys.

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The Monte Carlo code ERO simulates the three-dimensional transport of impurity particles in a background plasma using the test particle approximation. It treats the interaction of the plasma ions, atoms and of the impurities with the plasma facing components (PFC).ERO modelling for ITER estimates the lifetime of the inner target (erosion of 0.5 cm) to about 7000 shots with a shot length of 400s. The maximum allowed tritium retention due to eroded carbon not redeposited locally on the target plates would be already reached after 380-440 shots. Strike point sweeping might increase the target life time by a factor of about 4 while tritium retention seems not to be influenced.Apart from transient events especially material mixing effects of the elements foreseen for ITER as PFC (carbon, beryllium and tungsten) introduce uncertainties in the prediction. The injection of hydrocarbon ( 13 CH4) through spherical shaped limiters (one made of tungsten, one of graphite) in TEXTOR reveal that carbon has a reduced deposition efficiency on tungsten compared to graphite. This effect has not been taken into account until now in the modelling by the ERO code. The surface model of the code has therefore been substituted by a customized version of the Monte Carlo Code SDTrimSP which will help to clarify the effects of material mixing. A first successful test simulation shows that the depth distributed concentration of PFC influences sputtering yields.

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“…Within the field of magnetic fusion research, elements currently tested as appropriate materials for first-wall or divertor components in Tokamak devices (plasma-facing materials), including the International Thermonuclear Experimental Reactor (ITER) project, consider graphite, Fe, and C and Si composites, among other elements [1][2][3]. The effect of intense irradiation (sputtering) of these materials by protons, deuterons, or alpha particles is a subject of central interest for magnetic fusion research [2,4].…”

Section: Introductionmentioning

confidence: 99%

Unified description of interactions and energy loss of particles in dense matter and plasmas

Archubi

Arista

2020

Phys. Rev. A

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In this work, we propose a unified model to evaluate processes of electronic interactions of charged particles with hot and dense matter, including energy losses, mean free paths, and thermalization ranges of protons or other light ions. To formulate this method, we introduce modifications to the extended-wave-packet method, which allows one to describe and evaluate the effects of ionization as well as changes in target density and temperature. The ionization of the target leads to the formation of a dense surrounding plasma with distinct energy-absorption properties. We use this unified method to evaluate the contributions of inner shells and free electrons (produced by the target ionization) to the energy loss of protons in Si, C, and Fe targets, on an extensive range of parameters that include low, intermediate, and high energies, with densities and temperatures going from normal laboratory conditions to very high values, such as those of interest for inertial fusion and astrophysical studies.

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First wall and divertor plate sputtering in a tokamak reactor

Cited by 23 publications

References 0 publications

Evaluation of energy and particle impact on the plasma facing components in DEMO

Evaluation of energy and particle impact on the plasma facing components in DEMO

Impurity Transport Modelling in Edge Plasmas of Fusion Devices with the Monte Carlo Code ERO

Unified description of interactions and energy loss of particles in dense matter and plasmas

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