2021
DOI: 10.1080/15361055.2020.1843885
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Impact of High-Power Heat Load and W Surface Carbidization on Its Structural-Phase Composition and Properties

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Cited by 10 publications
(4 citation statements)
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“…The experiments were conducted within the temperature range from 700 °C to 1700 °C with a pitch of 100 °C with an irradiation for 1 h. The choice of this range is due to the calculation of the temperature distribution in the monoblock element carried out in [22] taking into account the uniform thermal load on the side of the surface W facing the plasma according to the initial data on the thermal power in the ITER. The choice of a constant value for the duration of irradiation was based on the results of experiments carried out earlier in [22][23][24].…”
Section: Methodsmentioning
confidence: 99%
“…The experiments were conducted within the temperature range from 700 °C to 1700 °C with a pitch of 100 °C with an irradiation for 1 h. The choice of this range is due to the calculation of the temperature distribution in the monoblock element carried out in [22] taking into account the uniform thermal load on the side of the surface W facing the plasma according to the initial data on the thermal power in the ITER. The choice of a constant value for the duration of irradiation was based on the results of experiments carried out earlier in [22][23][24].…”
Section: Methodsmentioning
confidence: 99%
“…Earlier, we carried out work on modeling the thermal load on plasma-converted tungsten under the conditions of ITER regular operation [ 38 ]. Based on the simulation results, the temperature values for plasma irradiation were calculated to simulate a thermal load corresponding to heat flows in ITER, which was 905 °C (corresponds to ~10 MW/m 2 stationary) and 1750 °C (corresponds to ~20 MW/m 2 pulsed).…”
Section: Experimental Partmentioning
confidence: 99%
“…The impact power of the plasma-beam discharge varied depending on the calculated temperature of the tungsten surface, as described above [ 38 ]. The ion current on the sample was measured by an ammeter of the power supply, which provided a potential supply of minus 2000 V. The current density was determined by placing the diaphragm in front of the target node with an aperture with a diameter of 10 mm.…”
Section: Experimental Partmentioning
confidence: 99%
“…Materials science studies conducted as part of the implementation of international programs for the creation of fusion reactors ITER and DEMO have shown that one of the best materials for use as an PFM (plasma-facing material) [1] in controlled fusion plants is liquid lithium and materials based on it [2,3,4]. The use of liquid lithium as a plasma-facing material is especially promising if lithium is enclosed in a so-called capillary-porous system (CPS) [5,6].Currently, there are many studies in the world conducted with lithium CPS, which once again confirms the interest in this material [7,8,9,10,11,12,13].Work on this topic is also being carried out at the Kazakhstan Materials Science Tokamak KTM [14,15,16,17,18,19,20].…”
Section: Introductionmentioning
confidence: 99%