Keywords: Tokamaks; Stellarators; Magnetohydrodynamic (MHD); Plasma transport and confinement; Divertor; 52.55.Fa; 52.55.Hc; 52.30.Cv; 52.25.Fi; 52.55.-s; 52.55.Rk;
مقالات ISI (ترجمه نشده)
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Effects of the divertor tile geometries and magnetic field angles on the heat fluxes to the surface
Keywords: 52.40.Hf; 52.55.Rk; 52.65.-y; Edge plasma; Divertor gap; Heat flux; Particle-in-cell;
Two-dimensional numerical study of ELMs-induced erosion of tungsten divertor target tiles with different edge shapes
Keywords: Divertor tile; Edge shape; ELMs; Melting52.55.Fa; 52.55.Rk; 52.40.Hf; 52.65.−y
Mitigation of edge localised modes with magnetic perturbations in ASDEX Upgrade
Keywords: 52.55.Fa; 52.55.Rk; 52.55.TnTokamaks; ASDEX Upgrade; MHD control; Edge localised modes
Finalizing the ITER divertor design: The key role of SOLPS modeling
Keywords: 52.65.Ww; 52.55.Rk; 52.40.Hf; 52.55.Fa; 52.25.XzITER; Divertor modeling; SOLPS; B2-Eirene
Effect of magnetic field on characteristics of divertor plasma and divertor erosion rate: PIC simulation
Keywords: 52.65.Rr; 52.55.Rk; 52.35.Hr; 52.40.HfDivertor plasma; Particle-In-Cell; Lower hybrid wave; Plasma surface interaction; Erosion
Super X divertors for solving heat and neutron flux problems of fusion devices
Keywords: 52.55.Rk; 52.55.Fa; 52.55.Dy; 52.25.Xz; 52.25.VyDivertor; Heat flux; High power density; Neutron shielding
ITER research plan of plasma–wall interaction
Keywords: 52.40.Hf; 52.55.Fa; 52.55.Rk
Pressure balance between midplane and inner and outer divertor in ASDEX Upgrade H-mode discharges
Keywords: 52.55.Fa; 52.55.Rk; 52.25.Fi
Divertor heat load in ITER-like advanced tokamak scenarios on JET
Keywords: 52.55.Fa; 52.55.Rk; 52.70.Kz;
Radiation process of carbon ions in JT-60U detached divertor plasmas
Keywords: 34.80.Lx; 52.20.âj; 52.25.Vy; 52.55.Fa; 52.55.Rk;
2D divertor design calculations for the national high-power advanced torus experiment
Keywords: 52.55.Fa; 52.55.Rk;
Radiating divertor experiments in the HL-2A tokamak
Keywords: 52.55.Rk; 52.40.Db; 52.25.Ya; 52.40.Hf;
Sensitivity of injected argon behavior to changes in magnetic balance in double-null plasmas in DIII-D
Keywords: 52.55.Fa; 52.25.V; 52.55.Rk; 28.52.Cx;
Highly radiating type-III ELMy H-mode with low plasma core pollution
Keywords: 52.25.Vy; 52.40.Hf; 52.55.Fa; 52.55.Rk;
Simulation of redeposition of carbon/hydrocarbon on a material surface with castellated structures
Keywords: 52.40.Hf; 52.55.Rk; 52.65.Pp
Model prediction of impurity retention in stochastic magnetic boundary and comparison with edge carbon emission in LHD
Keywords: 52.55.Fa; 52.55.Rk; 52.55.Fi; 52.65.Pp;
Current understanding of divertor detachment: Experiments and modelling
Keywords: 52.20−j; 52.25.Vy; 52.30.Ex; 52.55.Rk; 52.55.Fa
3D analysis of impurity transport and radiation for ITER limiter start-up configurations
Keywords: 52.40.Hf; 52.55.Rk; 52.65.Kj; 52.65.Pp
Fusion–Fission Transmutation Scheme—Efficient destruction of nuclear waste
Keywords: 52.55.Rk; 52.55.Fa; 28.41.Kw; 28.41.Vx; 28.50.FtFusion–Fission Hybrid; Compact fusion neutron source; Transmutation; Fuel cycle; Nuclear waste destruction; High power density
Physics and engineering issues associated with edge localized mode control in ITER
Keywords: 52.55a; 52.55.Rk; 52.35.PyDIII-D; ELMs; ITER
Fuel retention in tokamaks
Keywords: 51.40.HF; 52.55.Fa; 52.55.Rk
Study of the specific detachment characteristics of HL-2A
Keywords: D0500; H0100; H0400; T0100; 52.55.Rk; 52.55.Fa; 52.40.âw; B2/EIRENE; Divertor plasma; Divertor geometry; Divertor modeling;
Compatibility of the radiating divertor with high performance plasmas in DIII-D
Keywords: 52.25.Vy; 52.25.Xz; 52.40.Hf; 52.55.Fa; 52.55.Rk; Argon; Divertor; Divertor plasma; Impurity screening; DIII-D;
A new edge-based energy scaling law for W7-AS and its implications for boundary-island divertor operation
Keywords: P0600; 52.25.âb; 52.25.Fi; 52.55.Hc; 52.55.Rk; W7-AS; Energy confinement; Scaling law; Edge plasma; Island divertor;
ELM-wall interaction on JET and ITER
Keywords: 52.30.âq; 52.40.Hf; 52.55.Fa; 52.55.Rk; ELM; Divertor; JET; ITER; Power deposition;
Non-axisymmetric SOL-transport study for tokamaks and stellarators
Keywords: 52.40.Hf; 52.55.Rk; 52.65.−y; 52.65.PpEdge modeling; Island divertor; ITER; TEXTOR-DED; W7-AS
Migration of 13C and deposition at ASDEX Upgrade
Keywords: C0100; D0500; R0900; 52.40.Hf; 52.55.Fa; 52.55.Rk; 82.80.Ms; ASDEX Upgrade; Divertor; Carbon based materials; Erosion; Deposition;
Effect of the tokamak size in edge transport modelling and implications for DEMO
Keywords: P0500; P0600; T0100; 52.55.Fa; 28.52.âs; 52.65.ây; 52.55.Rk; 52.25.Vy; B2/EIRENE; Edge modelling; Edge pedestal; Fusion reactor; ITER;
Divertor transport study in the large helical device
Keywords: P0500; P0600; T010052.55.Hc; 52.55.Rk; 52.25.Fi; 52.65.PpLHD; 3D Edge plasma; Edge modelling; Stochastic boundary
Pedestal, SOL and divertor plasma properties in DIII-D RMP ELM-suppressed discharges at ITER relevant edge collisionality
Keywords: 52.55.Fa; 52.40.Hf; 52.55.Rk; 52.25.Vy; 52.70.KzDIII-D; ELM; Stochastic boundary; Carbon impurities; Edge plasma
Modeling of asymmetric redeposition distribution between inner and outer regions of the W-shaped divertor in JT-60U
Keywords: D0500; P0500; R0900; T0100; 52.40.Hf; 52.55.Fa; 52.55.Rk; 52.65.Pp; Co-deposition; Divertor; Edge modeling; Erosion and deposition; Hydrocarbons; JT-60U;
Modeling of parasitic plasma under the divertor roof baffle
Keywords: R0900; S1300; T0100; 52.25.Jm; 52.40.Kh; 52.55.Rk; 52.65.Rr; Divertor plasma; Edge modeling; Radiation; Sheaths;
Studies on 13C deposition in ASDEX Upgrade
Keywords: C0100; D0500; R0900; 52.40.Hf; 52.55.Fa; 52.55.Rk; 82.80.Ms; ASDEX Upgrade; Divertor; Carbon based materials; Erosion & Deposition;
Heat deposition patterns on the target plates of the dynamic ergodic divertor
Keywords: P0500; 52.55.Fa; 52.55.Rk; Divertor plasma; Edge plasma; Power deposition; Stochastic boundary; Thermography;
Simple Core-SOL-Divertor model and its application to operational space of HT-7U
Keywords: P0600; T0100; 28.52.Av; 52.55.Fa; 52.55.Rk; Divertor modeling; Particle balance; Power balance; HT-7U;