Comparison of High-Energy He+ and D+ Irradiation Impact on Tungsten Surface in the IR-IECF Device

Semsari, S.; Zakeri, Alireza; Sadighzadeh, A.; Khademzadeh, Saeed; Sedaghat, M.; Torabi, Mohammadamin; Damideh, Vahid

doi:10.1007/s10894-012-9540-6

Cited by 10 publications

(3 citation statements)

References 14 publications

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“…In the following we investigate two of these possible causes. The most obvious is the formation of a distorted surface layer, as shown in several experiments (see references [1][2][3][4][5][6][7][8][9][10][11]), which is investigated as a function of fluence and temperature in section 3.2.1. The second is the dependence of the sputtering yield on the crystal orientation.…”

Section: Investigation Of Possible Mechanismsmentioning

confidence: 99%

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Tungsten erosion under combined hydrogen/helium high heat flux loading

et al. 2014

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We investigated the erosion behaviour of tungsten under irradiation with a fusion reactorrelevant H/He mixture of 94%/6% at a power density of 10 MW/m². The investigated surface temperatures range up to 2000°C and the range of the applied fluence was up to 7×10 25 m -2 . The erosion yield we observe exceeds the value expected from physical sputtering data by a factor of 2. In addition we observe an Arrhenius-like increase of the erosion yield with temperature with an activation energy of 0.04 eV.

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Section: Investigation Of Possible Mechanismsmentioning

confidence: 99%

“…Detailed studies of the morphology development upon irradiation with 30 or 100 keV He ions have recently been reported from electrostatic confinement devices [9,10,11].…”

Section: Introductionmentioning

confidence: 99%

Tungsten erosion under combined hydrogen/helium high heat flux loading

et al. 2014

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“…The PF devices have also been used as a tool to experimentally simulate the effects of radiations on different materials proposed for different parts of nuclear fusion devices based on inertial and magnetic plasma confinement at locations like National Ignition Facility (NIF, USA), International Thermonuclear Experimental Reactor (ITER, France), in TOKAMAK and in other plasma devices as well as accelerators [21,22,[25][26][27][28][29][30][31]. The tritium retention in the cracks in the plasma facing materials (PFM) and neutron induced radioactivity of materials over long operation of the fusion reactors are main concern in the selection of materials for various components of the fusion devices.…”

Section: Introductionmentioning

confidence: 99%