Abstract:The composition, morphology and structure of the mixed layers deposited onto the surface (deposits) after a preliminary carboboronization procedure (B/C : H layers deposition) and subsequent plasma–wall interaction in the different areas of the Globus-M spherical tokamak have been analysed. Globus-M is almost completely covered by recrystallized graphite protection tiles (currently about 90% of its inner vessel area facing to plasma). The deposit properties were examined by different diagnostic techniques (ele… Show more
“…In this context, the necessity of ensuring long term steady state operation of the FNS ST requires additional experimental and theo retical studies on the possibility of operation under partial detachment conditions. At present, the physics of the divertor plasma is being actively studied experimentally at the Russian spherical tokamak Globus M, which in some param eters (in particular, high density of the input power) approaches the FNS ST project [48,49]. The authors of the present paper are preparing experiments at this tokamak to verify the proposed model and the above assumptions.…”
A concept of the divertor and the technology for organizing the edge plasma in a fusion neutron source based on a spherical tokamak (FNS ST) are described. The experimental data on the characteristics of the peripheral plasma in modern tokamaks are extrapolated to the FNS ST conditions with the help of semi analytical models. The effects depending on the magnetic configuration and on the geometry and mate rials of the divertor and the first wall elements are considered. Possible designs of the FNS ST divertor and the first wall are described. Using an original model, it is shown that the maximum density of the heat flux at the divertor plates in a double null magnetic configuration does not exceed 5-6 MW/m 2 , which complies with modern engineering capabilities. Methods for further improvement of the FNS ST divertor concept are analyzed.
“…In this context, the necessity of ensuring long term steady state operation of the FNS ST requires additional experimental and theo retical studies on the possibility of operation under partial detachment conditions. At present, the physics of the divertor plasma is being actively studied experimentally at the Russian spherical tokamak Globus M, which in some param eters (in particular, high density of the input power) approaches the FNS ST project [48,49]. The authors of the present paper are preparing experiments at this tokamak to verify the proposed model and the above assumptions.…”
A concept of the divertor and the technology for organizing the edge plasma in a fusion neutron source based on a spherical tokamak (FNS ST) are described. The experimental data on the characteristics of the peripheral plasma in modern tokamaks are extrapolated to the FNS ST conditions with the help of semi analytical models. The effects depending on the magnetic configuration and on the geometry and mate rials of the divertor and the first wall elements are considered. Possible designs of the FNS ST divertor and the first wall are described. Using an original model, it is shown that the maximum density of the heat flux at the divertor plates in a double null magnetic configuration does not exceed 5-6 MW/m 2 , which complies with modern engineering capabilities. Methods for further improvement of the FNS ST divertor concept are analyzed.
“…Морфология и элементный состав облицовочных плиток [7,8], пыли и крупных частиц, появив-шихся в результате эксплуатации Глобус-М в режиме рабочих разрядов и процедур очистки, были изучены на электронно-зондовом микроанализаторе Камебакс (фирма «Камека», Франция) методами растровой электронной микроскопии (РЭМ) и рентгеноспектрального микроанализа (РСМА) при ускоряющем напряжении 15 кВ и токе 1 нА. Глубина анализа элементного состава ~3 мкм для угле-родной матрицы и ~1 мкм для металлической.…”
Section: экспериментальная техникаunclassified
“…Рентгенофазовый анализ (РФА) образцов (5×10×5 мм), вырезанных из исходных и облучённых плиток [7,8], а также проб пыли и крупных частиц, был выполнен на дифрактометре ДРОН-3 с медной трубкой (λ Cu = 0,154 нм) и с графитовым монохроматором. Регистрация дифрагирующих пучков осуществлялась в интервале углов 2 от 10º до 90º с шагом 0,05º и временем экспозиции в каждой точке 1,5 с (глубина анализа составляла ~10 мкм для углеродной матрицы и ~5 мкм для металлической).…”
Section: экспериментальная техникаunclassified
“…и примесей (ат. %): Fe (4,8), Cr (3,3), Ti (2,9), Ni (0,9), Si (0,1). Толщина углеродной оболочки 2-3 мкм при диа-метре сферы 10 мкм.…”
Section: экспериментальные результаты и их обсуждениеunclassified
“…Механизмы разрушения графитов при облучении интенсивными потоками плазмы были исследованы на установках МК-200 и КСПУ [6]. Морфологические, композиционные изменения и структурно-фазовые превращения в плазмоконтактирующих материалах токамака Глобус-М были рассмотрены в работах [7][8][9].…”
Experiments and simulations to achieve high values of plasma parameters at the Globus-M spherical tokamak (ST) at moderate auxiliary heating power (0.2-0.8 MW) are described. Important distinguishing features are the low edge safety factor range, which is unusual for spherical tokamaks, 2.7 < q < 5 and small plasma-outer wall space (3-5 cm). High ion heating efficiency with NB injection was demonstrated. Results of numerical simulation of fast ion trajectories are described and fast ion generation during NB injection and ICR heating is discussed. Also results on their confinement and slowing down processes investigation are presented. Reasons for achievement of high IC heating efficiency are outlined. Reliable H-mode regime achievement is described. Transport ASTRA modeling demonstrated that during NB heated H-mode ion heat diffusivity remains neoclassical and the particle diffusion coefficient inside transport barrier decreases significantly. RGTi divertor tile analysis was performed after irradiation by plasma during big number of shots (10000 shots in average). Mixed layer composition is measured and deuterium retention in different tokamak first wall area is estimated. Plasma jet injection experiments with upgraded plasma jet are described. Jet penetration to the plasma center with immense increase of density and temperature drop is proved and analogy with pellet injection is outlined.
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