2018
DOI: 10.1088/1361-6587/aae339
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Simulations on W impurity transport in the edge of EAST H-mode plasmas

Abstract: This paper provides an investigation of the production/transport properties of W impurity in the edge of experimental advanced superconducting tokamak (EAST) H-mode discharges with upper-singlenull configurations by using DIVIMP Monte-Carlo code. The background plasmas are provided by SOLPS5.0 calculations. Firstly, to address the detailed dependence of W impurity behaviors on plasma conditions in the scraped-off layer (SOL)/divertor region of EAST, two pre-edge localized mode (ELM) cases with divertor plasmas… Show more

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Cited by 14 publications
(11 citation statements)
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“…The W impurity transport along magnetic field lines in DIVIMP is based on the forces acting on it. The radial cross-field transport is assumed to be anomalous with the prescribed cross-field diffusion coefficient D ⊥ = 1.0 m 2 s −1 , which has been widely used in previous simulation studies for ASDEX-U [18], DIII-D [19], JET [5,20,21], EAST [22] and ITER [23,24].…”
Section: The Background Plasma and The Simulation Setupmentioning
confidence: 99%
“…The W impurity transport along magnetic field lines in DIVIMP is based on the forces acting on it. The radial cross-field transport is assumed to be anomalous with the prescribed cross-field diffusion coefficient D ⊥ = 1.0 m 2 s −1 , which has been widely used in previous simulation studies for ASDEX-U [18], DIII-D [19], JET [5,20,21], EAST [22] and ITER [23,24].…”
Section: The Background Plasma and The Simulation Setupmentioning
confidence: 99%
“…DIVIMP is a two-dimensional (2D) impurity transport code that uses the Monte-Carlo method [72,73] and is widely applied for modeling the impurity transport in the plasma edge owing to its simple structure, short calculation time, and applicability in plasma of any collisionality [19,23,27]. In this work, DIVIMP is employed to simulate the transport of W, which is treated as a trace impurity in the plasma background provided by SOLPS-ITER simulation.…”
Section: Simulation Schemementioning
confidence: 99%
“…Therefore, it is of great importance to understand the transport of W impurities in the scrape-off layer (SOL), which determines the source of the tungsten contamination inside the confined plasma. Many efforts have been conducted on this subject for various existing tokamaks, such as EAST [19][20][21][22], DIII-D [23,24], JET [25][26][27], and ASDEX-Upgrade [28], and for future fusion reactors, such as ITER [29,30], CFETR [31][32][33], and DEMO [34].…”
Section: Introductionmentioning
confidence: 99%
“…It is important to ensure that the rate of ionization is not too high to prohibit sufficient beam penetration, nor too low to allow a significant portion of the beam to pass straight through the plasma [16]. Therefore, the common plasma impurities like carbon, nitrogen, and oxygen are of special interest as well as metallic species sputtered from the container walls [17][18][19]. So, the accurate knowledge of various cross sections when the multiply charged ions of these elements colliding with hydrogen atoms are key important.…”
Section: Introductionmentioning
confidence: 99%