Effects of background plasma characteristics on tungsten impurity transport in the SOL/divertor region using IMPGYRO code

Yamoto, S.; Homma, Y.; Hoshino, Kazuo; Sawada, Yukimasa; Bonnin, X.; Coster, D.; Schneider, R.; Hatayama, A.

doi:10.1016/j.jnucmat.2014.10.013

Cited by 13 publications

(15 citation statements)

References 13 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, with the use of tungsten as divertor and wall armour material increasingly being employed on present devices, as well as exclusively in the divertor for ITER [27], it is essential that SOLPS-ITER provide some means to include it. A promising approach being pursued is the coupling of B2.5-Eirene with kinetic trace impurity following codes such as IMPGYRO [28]. 3 A very valuable validation exercise, reported in [29,30], matching the code output to a detailed two-point model analysis of the SOL and divertor plasma, was performed for SOLSP4.3.…”

Section: Additional Physicsmentioning

confidence: 99%

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Bonnin¹,

Dekeyser²,

Pitts³

et al. 2016

Plasma and Fusion Research

236

200

View full text Add to dashboard Cite

We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas in the edge region of fusion devices. This package brings together previously existing SOLPS implementations and aims to become the new standard SOLPS version. We summarize the benchmarking work done to ensure backward compatibility with previous work, with a strong requirement on maintaining the viability and usability of the already extensive database of SOLPS runs used for the ITER divertor design and edge plasma physics studies worldwide over the years. The SOLPS-ITER package includes not only the plasma (B2.5) and neutral (Eirene) transport solvers, but also a large set of software tools for input file build-up, conversion of old runs, inline run analysis, and post-processing, all within a standardized portable run environment and version control system. Ongoing and planned upgrades to the code, such as extending the computational domain to the full vacuum vessel wall and a new graphical user interface, are also discussed.

show abstract

Section: Additional Physicsmentioning

confidence: 99%

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Bonnin¹,

Dekeyser²,

Pitts³

et al. 2016

Plasma and Fusion Research

236

200

View full text Add to dashboard Cite

show abstract

“…Various SOL-divertor plasma code packages, therefore, have been developed and benchmarked with experimental results such as SOLPS (B2-EIRENE) [1], SONIC [2,3] and UEDGE [4]. Experimental results of existing devices, however, cannot always be reproduced satisfactorily with these code packages and efforts have been made to resolve this issue from, for example, kinetic effects of a plasma [5], drifts [6,7], supersonic plasma flows [8], neutral models [5,6], impurity models [9] and plasmawall-interactions (PWI) models [7,8] points of view.…”

Section: Introductionmentioning

confidence: 99%

Benchmarking of B2 Code with a One-Dimensional Plasma Fluid Model Incorporating Anisotropic Ion Pressures on Simple Mirror Configurations

Togo

Reiser

Börner

et al. 2018

Plasma and Fusion Research

View full text Add to dashboard Cite

A plasma fluid code B2 has been benchmarked with a one-dimensional plasma fluid model incorporating the anisotropic ion pressures (AIP model) on simple mirror configurations. In a low collisionality case, profiles of plasma parameters of the B2 code deviate from those of the AIP model. The validity of the viscous-flux approximation is investigated by direct comparisons with the anisotropic part of the ion pressure indicating the invalidity of the viscous-flux approximation is considered to be responsible to deviations of profiles. In addition, supersonic plasma flows downstream from the mirror throat are observed.

show abstract

“…Physics model implemented in the IMPGYRO code in the present study is the same as those in Ref. [2]. Effects of magnetic drifts have been automatically taken into account, because the full orbit of each test particle has been followed in IMPGYRO code.…”

Section: Impgyro Calculation Setupsmentioning

confidence: 99%

“…In the previous study [2], we have investigated tungsten impurity transport process parallel to the magnetic field by the IMPGYRO code. The calculation has performed under two different background plasma parameters calculated by SOLPS realistic tokamak geometry with lower single-null X-point.…”

Section: Introductionmentioning

confidence: 99%

“…In this paper, as the first step toward implementing whole the neoclassical effect into the IMPGYRO model, the effect of the neoclassical self-diffusion process of the impurity particles in realistic tolamak geometry has been investigated. In order to understand the effects of neoclassical self-diffusion and its magnitude, comparison between the full-gyro orbit motion model by IMPGYRO [1,2,11] and the guiding center approximation model has been performed under the background plasma parameter obtained from numerical code-package SOLPS5.0 [12].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Effects of Classical and Neo‐classical Cross‐field Transport of Tungsten Impurity in Realistic Tokamak Geometry

Yamoto

Homma

Inoue

et al. 2016

Contrib. Plasma Phys.

Self Cite

View full text Add to dashboard Cite

The initial simulation study of the neoclassical perpendicular self-diffusion transport in the SOL/Divertor regions for a realistic tokamak geometry with the IMPGYRO code has been performed in this paper. One of the most unique features of the IMPGYRO code is calculating exact Larmor orbit of the test particle instead of assuming guiding center approximation. Therefore, effects of the magnetic drifts in realistic tokamaks are naturally taken into account in the IMPGYRO code. This feature makes it possible to calculate neoclassical transport processes, which possibly become large in the SOL/divertor plasma. Indeed, neoclassical self-diffusion process, the resultant effect of the combination of magnetic drift and Coulomb collisions with background ions, has already been included in the IMPGYRO model. In the present paper, prior to implementing the detailed model of neoclassical transport process into IMPGYRO, we have investigated the effect of neoclassical selfdiffusion in a realistic tokamak geometry with lower single null X-point. We also use a model with guiding center approximation in order to compare with the IMPGYRO full orbit model. The preliminary calculation results of each model have shown differences in the perpendicular average velocity of impurity ions at the top region of the SOL. The mechanism which leads to the difference has been discussed.

show abstract

Effects of background plasma characteristics on tungsten impurity transport in the SOL/divertor region using IMPGYRO code

Cited by 13 publications

References 13 publications

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Benchmarking of B2 Code with a One-Dimensional Plasma Fluid Model Incorporating Anisotropic Ion Pressures on Simple Mirror Configurations

Effects of Classical and Neo‐classical Cross‐field Transport of Tungsten Impurity in Realistic Tokamak Geometry

Contact Info

Product

Resources

About