Персона: Маренков, Евгений Дмитриевич
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Институт лазерных и плазменных технологий
Стратегическая цель Института ЛаПлаз – стать ведущей научной школой и ядром развития инноваций по лазерным, плазменным, радиационным и ускорительным технологиям, с уникальными образовательными программами, востребованными на российском и мировом рынке образовательных услуг.
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Евгений Дмитриевич
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- ПубликацияТолько метаданныеShielding of liquid metal targets in plasma of linear devices(2020) Marenkov, E. D.; Pshenov, A. A.; Kukushkin, A. S.; Маренков, Евгений Дмитриевич© 2020 Author(s).We apply a 0D model of shielding for simulations of liquid Li exposure experiments in He plasma of the Magnum-PSI linear device. The model accounts for all the most essential processes in the vapor cloud and plasma-surface interactions. The simulation results are in good agreement with the target surface temperature measurements. A factor of 10 increase in the erosion flux leads to a 100 °C decrease in the surface temperature, still giving a reasonable agreement with experiments. Therefore, the temperature measurements are inconclusive with respect to determining whether enhanced erosion takes place or not. We observe that only 10% of the eroded material is redeposited, while several other works suggest up to 99% redeposition. We show that low redeposition is a consequence of the low electron temperature, about 0.3 eV, in the vapor cloud and that the ratio of the ionization length to the transverse cloud size is the critical parameter to look at. Hence, the redeposition factor is not a universal quantity and can vary in quite a broad range depending on the plasma parameters and machine geometry.
- ПубликацияТолько метаданныеOn the role of hydrogen radiation absorption in divertor plasma detachment(2019) Krasheninnikov, S. I.; Pshenov, A. A.; Kukushkin, A. S.; Marenkov, E.; Маренков, Евгений ДмитриевичTransition to the detached divertor regime that allows lowering the peak power loads on the divertor targets to a tolerable level requires low plasma temperature T-e similar to 1 eV and high plasma density n(e) similar to 10(21) M-3 in front of the target. Under such conditions, radiation trapping of the Lyman lines of hydrogen isotopes becomes important. It can influence both energy balance and the ionization/recombination rates significantly. Nevertheless, opacity is typically neglected in the 2D edge transport codes used to study the divertor plasma detachment. We report on the first in-depth investigation of radiation opacity effects on transition to detachment. Simulations are performed with the SOLPS 4.3 code package using a DIII-D size tokamak as a particular example. It is found that in pure hydrogen plasma suppression of the neutral hydrogen radiation loss due to the photon absorption makes reaching the detached plasma regime more difficult. A significantly higher average separatrix plasma pressure is required to reach a similar degree of detachment. Adding plasma impurities compensates for the reduced neutral radiation and offsets the effect of opacity. In a carbon device, where the impurity source is due to erosion of the divertor components and is strongly connected to the edge plasma density, the absorbed fraction of the hydrogen radiation is easily compensated with the increasing carbon radiation loss. However, nowadays, in the more relevant case of the full-metal wall and seeded impurity with the feedback-controlled content, the increase of the edge plasma density alone is insufficient to compensate for trapping of the hydrogen radiation. In this case, achievement of the desired degree of detachment requires higher average separatrix plasma pressure or seeded impurity content than those obtained from the transparent plasma model.
- ПубликацияТолько метаданныеModeling the vapor shielding of a liquid lithium divertor target using SOLPS 4.3 code(2021) Marenkov, E. D.; Kukushkin, A. S.; Pshenov, A. A.; Маренков, Евгений ДмитриевичIn this letter, we report the very first results of SOLPS4.3 simulations of a liquid lithium (Li) divertor, including vapor shielding effects. A peculiarity of Li as a target coating material is the strong dependence of the erosion rate on the target temperature. We have implemented a new erosion model in SOLPS, taking this dependence into account. Simulations of the T15-MD tokamak divertor with Li-coated divertor targets have been performed. Li erosion is determined by physical sputtering, evaporation, and thermal sputtering. The results of the simulations show that a shielding effect occurs, providing a reduction of the target heat flux to values below 8 MW m(-2). At the same time, the upstream plasma dilution in the high-power regimes, where shielding is most efficient, is very strong, meaning that in practical terms, it may be difficult to rely on the shielding effect for heat flux control in the configuration considered.
- ПубликацияТолько метаданныеSimulation of lithium flow, redeposition, and vapor shielding in liquid lithium divertor of T-15MD tokamak with SOLPS 4.3 code(2022) Marenkov, E. D.; Pshenov, A. A.; Kukushkin, A. S.; Маренков, Евгений Дмитриевич
- ПубликацияТолько метаданныеRecent Progress in Some Issues of Divertor Physics under Detachment Conditions(2023) Stepanenko, A. A.; Marenkov, E. D.; Pshenov, A. A.; Kukushkin, A. S.; Степаненко, Александр Александрович; Маренков, Евгений Дмитриевич
- ПубликацияТолько метаданныеDivertor plasma opacity effects(2023) Pshenov, A. A.; Kukushkin, A. S.; Gorbunov, A. V.; Marenkov, E. D.; Маренков, Евгений Дмитриевич