Globus-M plasma edge modeling with B2SOLPS5.2 code

Vekshina, E. O.; Senichenkov, I.; Rozhansky, V.; Хромов, Н. А.; Курскиев, Г. С.; Патров, М. И.; Team, Globus-M

doi:10.1088/0741-3335/58/8/085007

Cited by 14 publications

(21 citation statements)

References 8 publications

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“…The test calculation was made to confirm applicability of this code for beryllium transport. Earlier the SOLPS-ITER code was used for modeling of different tokamaks with different sorts of impurities (such as He, N, Ne, C) such as ITER [3], Globus-M [4], ASDEX Upgrade [5], JET [6], DIII-D [7], Alcator C-Mod [8] and others.…”

Section: Introductionmentioning

confidence: 99%

SOLPS-ITER modeling of beryllium trace impurity in ITER

Makarov

2018

MATEC Web Conf.

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Beryllium transport modeling was carried out in the trace impurity regime by SOLPS-ITER code for tokamak ITER. It is valuable for developing of diagnostics protection from beryllium deposition. TRIM reflection model and Bogdanskii formula sputtering model were applied. The idea is to show possibility of using this code for beryllium transport. This code has key advantage comparing to other codes, which study beryllium transport, because in it the main plasma and impurities are described self-consistently. Therefore, if beryllium affect the background plasma, only this code can take this effect into account. Test calculations were performed with suppressed sputtering yield by 10 times, to reach trace impurity regime. Main features of behavior of beryllium in the tokamak were studied, however under restriction of static wall conditions. Sources, sinks, fluxes and density distribution were determined. In this test calculation plasma state kept unchanged as expected. Distribution of impinging and absorbed fluxes on the outer divertor plate were established in the position of divertor diagnostics. Main ways for the further improvement are suggested.

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Section: Introductionmentioning

confidence: 99%

SOLPS-ITER modeling of beryllium trace impurity in ITER

Makarov

2018

MATEC Web Conf.

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“…In this publication the modeling of 2D transport in the plasma edge was performed by SOLPS-ITER transport code [19,20], which is based on the B2 plasma solver and includes the self-consistent model for drifts, plasma currents and electric potential. The code is widely used on many machines like ITER [21], AUG [22], JET [23], MAST [24], Alcator-Cmod [25], Globus-M [26].…”

Section: Methodsmentioning

confidence: 99%

“…In present modeling these coefficients ( Fig. 2) are chosen the same as those used in the modeling of the Globus-M shot #34410 [26], except the ion heat conductivity (the anomalous contribution is introduced). 3 Results and Discussion…”

Section: Fig 1 Computational Mesh For the Solps-iter Codementioning

confidence: 99%

Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor

et al. 2018

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In according to a present understanding of Scrape-Off Layer (SOL) physics, future thermonuclear devices like ITER, DEMO and beyond, require high radiation regimes in order to reduce heat loads on tokamak divertor. Recent experiments at ASDEX Upgrade, JET and other tokamaks demonstrated that such regimes might be achieved by the seeding of the radiative impurities. In the present paper the modeling of the high radiation regimes and the transition to the detachment at the Globus-M2 spherical tokamak is performed by the SOLPS-ITER transport code. The obtained modeling results for GLobus-M2 tokamak demonstrate the trend similar to what is observed at larger machines, e.g. AUG and JET. The significant reduction of peak power density at the outer target plate and transition to the detachment with High Field Side High Density (HFSHD) formation at the inner plate was achieved with impurity seeding rate almost equal to the deuterium puff (in el/sec). However, unlike AUG, further increasing of the seeding rate leads not to a formation of the radiative X-point, but to a radiative collapse. This is caused by smaller machine size, which allows the impurity neutrals to penetrate easier into the confined region. It was noticed that starting with attached divertor the inner target transits to the detachment earlier than the outer one.

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“…В условиях описываемых экспериментов движение SP вдоль зондов в течение разряда (рис. пространственное разрешение описываемой диагностики по сравнению с более ранними измерениями [13]. Если на рассматриваемом интервале времени параметры плазмы меняются несущественно, то можно совместить на одном графике профили, записанные в разные моменты времени, сдвинув их вдоль большого радиуса с учетом скорости движения SP [7].…”

Section: измерение профилей параметров плазмы вблизи диверторных пластинunclassified

“…То есть в условиях разряда #34354 наличие значительного электронного тока на пластину вблизи SP, по-видимому, приводит к существенному занижению плотности теплового потока, вычисляемой согласно (2). Параметры краевой плазмы токамака Глобус-М для схожих разрядов моделировались кодом B2SOLPS5.2 с учетом всех дрейфов и токов [13]. Плотность тока на пластину, полученная в моделировании, имеет те же особенности, что и измеренная экспериментально -в области PFR ток направлен на пластину и его плотность меньше плотности ионного тока насыщения.…”

Section: измерение профилей параметров плазмы вблизи диверторных пластинunclassified

Исследование Пристеночной Плазмы Токамака Глобус-М С Помощью Массива Диверторных Ленгмюровских Зондов

Хромов¹,

Векшина²,

Гусев³

et al. 2021

Журнал Технической Физики

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Массив из десяти встроенных диверторных зондов был установлен на нижний купол сферического токамака Глобус-М. С его помощью проведены измерения профилей плавающего потенциала, электронной температуры, ионного тока насыщения и плотности потока тепла на дивертор. Продемонстрировано резкое изменение плавающих потенциалов зондов, находящихся вблизи внешней ветви сепаратрисы, при развитии периферийной неустойчивости. Ключевые слова: токамак, дивертор, пристеночная плазма, ленгмюровские зонды.

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Globus-M plasma edge modeling with B2SOLPS5.2 code

Cited by 14 publications

References 8 publications

SOLPS-ITER modeling of beryllium trace impurity in ITER

SOLPS-ITER modeling of beryllium trace impurity in ITER

Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor

Исследование Пристеночной Плазмы Токамака Глобус-М С Помощью Массива Диверторных Ленгмюровских Зондов

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