Numerical simulation study towards plasma detachment in the end cell of GAMMA 10/PDX by a coupled fluid‐neutral code

Islam, Md. Shahinul; Nakashima, Y.; Tatsumi, Ryoko; Hatayama, A.; Iijima, Takahiro

doi:10.1002/ctpp.201700122

Cited by 4 publications

(4 citation statements)

References 40 publications

(52 reference statements)

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“…Although the transport phenomena of H neutral particles is beyond the scope of the current research, we have investigated the H neutral profile by a kinetic code to validate the current fluid neutral assumption. A kinetic neutral code has been recently developed to investigate the behavior of neutral particles at the end-cell of GAMMA 10/PDX [24]. The Boltzmann equation has been solved by applying the Monte-Carlo technique to model the neutral particles.…”

Section: Applicability Of Current Fluid Neutral Modelmentioning

confidence: 99%

Study of end-cell plasma parameters of GAMMA 10/PDX by the LINDA code

Islam

Nakashima

Hatayama

et al. 2019

Plasma Phys. Control. Fusion

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This research numerically investigates the plasma behavior during neutral gases puffing into the west end-cell of the linear plasma confinement device GAMMA 10/PDX. A multi-fluid code named 'LINDA' is developed and applied at the west end-cell of the device to explore the processes of plasma detachment and energy loss mechanism during plasma-neutral interactions. The ion heat flux limiter is newly introduced in the LINDA code. In the paper, we investigate the influence of the ion heat flux limiter in our divertor plasma models to understand how the ion heat flux limiter affects the computed plasma parameters. The upstream plasma parameters are = ´= = n T T 1 10 m , 30 eV, and 100 eV. i 19 3 e iThe effect of ion heat flux limiting reduces the ion temperature and heat flux in the direction of the target plate. The ion temperature profile is shown to be similar when the heat flux limiting factor (α i ) is varied from 0.2 to 2.0. The effect of Hydrogen (H) and Argon (Ar) gas puffing has been investigated under the condition of ion heat flux limiting factors α i =1.0. The ion temperature is shown to be similar between Ar and without Ar puffing. On the other hand, T e reduces remarkably for Ar puffing by enhancing the radiation cooling of Ar. The ion and electron loss are greatly enhanced for combined puffing of Ar and H. The ionization loss is found to be slightly higher and the charge-exchange loss is found to be slightly lower during the ion heat flux limiting case. These outcomes may contribute to understanding the plasma detachment processes in fusion devices.

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Section: Applicability Of Current Fluid Neutral Modelmentioning

confidence: 99%

Study of end-cell plasma parameters of GAMMA 10/PDX by the LINDA code

Islam

Nakashima

Hatayama

et al. 2019

Plasma Phys. Control. Fusion

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“…Effects of pumping efficiency and radial transport coefficients were studied [20] and a quantitative analysis of the importance of transport and atomic processes, based on the two-point model [21,22], was performed. Alongside the efforts to adapt tokamak mean-field edge codes to LPDs, some attempts were also made to develop codes which implement plasma transport models in cylindrical geometry, both considering mean-field transport questions [23][24][25][26][27] and a consistent treatment of turbulence [28][29][30][31][32]. While this approach allows simplifications in the transport equations due to a simpler geometry, these codes are presently limited due to the absence or the highly simplified treatment of neutral species and their interactions with the background plasma.…”

Section: Introductionmentioning

confidence: 99%

Simulations of Argon plasmas in the linear plasma device GyM with the SOLPS-ITER code

Sala

Tonello

Uccello

et al. 2020

Plasma Phys. Control. Fusion

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Edge plasma codes, such as SOLPS, are widely used to study plasma transport in tokamaks scrape-off layers (SOL). The possibility to apply these codes to non hydrogenic plasmas and to linear plasma devices (LPDs) is gaining the interests of the fusion community. These facilities play a pivotal role in plasma-material interaction (PMI) studies for future fusion devices and may allow to test the code capabilities both in terms of geometry and simulated plasma species. In this contribution, we apply the SOLPS-ITER code for the simulations of Argon plasmas in the medium-flux linear machine GyM. A sensitivity scan over the pumping efficiency, transport coefficients and absorbed electron power was done, performing B2.5-EIRENE coupled simulations. A quantitative analysis of the different flux contributions is provided through the use of a twopoint modelling. Comparison with experiments shows a promising qualitative and quantitative agreement, with the sole exception of the simulated neutrals pressure. Dedicated EIRENE standalone simulations were performed to investigate this issue, also highlighting the role of neutral-neutral elastic collisions at high values of the puffing intensity.

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“…In the previous studies, the neutral profile is calculated by solving a 1D continuity equation under the constant neutral velocity. [ 12–18 ] A Kinetic Monte–Carlo Neutral Code (KMNC) is newly developed and the transport of hydrogen neutral particles was investigated under the condition of fixed background plasma parameters in the previous study. [ 18 ] In this present calculation case, both the fluid and the neutral code are numerically solved in the self‐consistence manner.…”

Section: Introductionmentioning

confidence: 99%

“…[ 12–18 ] A Kinetic Monte–Carlo Neutral Code (KMNC) is newly developed and the transport of hydrogen neutral particles was investigated under the condition of fixed background plasma parameters in the previous study. [ 18 ] In this present calculation case, both the fluid and the neutral code are numerically solved in the self‐consistence manner. The fluid code solves continuity, momentum, and electron and ion energy equations.…”

Section: Introductionmentioning

confidence: 99%

Impact of neutral gas puffing on the divertor power exhaust and particle control in GAMMA 10/PDX by the LINDA‐KNMC code

Islam

Nakashima

Hatayama

et al. 2021

Contributions to Plasma Physics

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This paper numerically investigates the impact of neutral gas puffing on the divertor power exhaust and particle control in GAMMA 10/PDX applying the plasma fluid code LINDA and the kinetic neutral code KMNC. The LINDA code is applied to GAMMA 10/PDX plasmas for understanding the physics of detachment and energy loss processes. The LINDA code is coupled with a Monte-Carlo neutral code for describing the hydrogen (H and H 2 ) neutral particles. The plasma ion temperature (T i ) is reduced towards the target plate with the increment of H 2 Gas-Puff rate. This paper also numerically investigates the impact of recombination processes on the detached formation. The ionization, charge-exchange, and recombination of H have been included as a particle and an energy sink and source parts of the fluid equations. The reaction rate coefficient of molecular activated recombination (MAR) has been recently introduced in the LINDA code. In this paper, we study numerically the effect of MAR on the detached plasma. The MAR plays a dominant role in making the detached plasma. The simulation clarified that H neutral particles injection can effectively generate the detached plasma by enhancing the plasma-neutral collisions processes.

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Numerical simulation study towards plasma detachment in the end cell of GAMMA 10/PDX by a coupled fluid‐neutral code

Cited by 4 publications

References 40 publications

Study of end-cell plasma parameters of GAMMA 10/PDX by the LINDA code

Study of end-cell plasma parameters of GAMMA 10/PDX by the LINDA code

Simulations of Argon plasmas in the linear plasma device GyM with the SOLPS-ITER code

Impact of neutral gas puffing on the divertor power exhaust and particle control in GAMMA 10/PDX by the LINDA‐KNMC code

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