Related references
Note: Only part of the references are listed.Prediction of divertor heat flux width for ITER using BOUT plus plus transport and turbulence module
Ze-Yu Li et al.
NUCLEAR FUSION (2019)
Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width
X. Q. Xu et al.
NUCLEAR FUSION (2019)
Physics basis for the first ITER tungsten divertor
R. A. Pitts et al.
NUCLEAR MATERIALS AND ENERGY (2019)
Impact of the plasma geometry on divertor power exhaust: experimental evidence from TCV and simulations with SolEdge2D and TOKAM3X
A. Gallo et al.
PLASMA PHYSICS AND CONTROLLED FUSION (2018)
Calculation of two-dimension radial electric field in boundary plasmas by using BOUT plus
N. M. Li et al.
COMPUTER PHYSICS COMMUNICATIONS (2018)
Access to pedestal pressure relevant to burning plasmas on the high magnetic field tokamak Alcator C-Mod
J. W. Hughes et al.
NUCLEAR FUSION (2018)
Calculation of the radial electric field with RF sheath boundary conditions in divertor geometry
B. Gui et al.
NUCLEAR FUSION (2018)
High-resolution heat flux width measurements at reactor-level magnetic fields and observation of a unified width scaling across confinement regimes in the Alcator C-Mod tokamak
D. Brunner et al.
NUCLEAR FUSION (2018)
Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths
B. Chen et al.
PHYSICS OF PLASMAS (2018)
The flush-mounted rail Langmuir probe array designed for the Alcator C-Mod vertical target plate divertor
A. Q. Kuang et al.
REVIEW OF SCIENTIFIC INSTRUMENTS (2018)
Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER
C. S. Chang et al.
NUCLEAR FUSION (2017)
Divertor heat flux simulations in ELMy H-mode discharges of EAST
T. Y. Xia et al.
NUCLEAR FUSION (2017)
Edge turbulence and divertor heat flux width simulations of Alcator C-Mod discharges using an electromagnetic two-fluid model
B. Chen et al.
NUCLEAR FUSION (2017)
Drift-based scrape-off particle width in X-point geometry
D. Reiser et al.
NUCLEAR FUSION (2017)
Exploring drift effects in TCV single-null plasmas with the UEDGE code
N. Christen et al.
PLASMA PHYSICS AND CONTROLLED FUSION (2017)
Analysis of drift effects on the tokamak power scrape-off width using SOLPS-ITER
E. T. Meier et al.
PLASMA PHYSICS AND CONTROLLED FUSION (2016)
Nonlinear fluid simulation of particle and heat fluxes during burst of ELMs on DIII-D with BOUT plus plus code
T. Y. Xia et al.
NUCLEAR FUSION (2015)
Kinetic modeling of divertor heat load fluxes in the Alcator C-Mod and DIII-D tokamaks
A. Y. Pankin et al.
PHYSICS OF PLASMAS (2015)
Boundary plasma turbulence simulations for tokamaks
X. Q. . Xu et al.
Communications in Computational Physics (2014)
Scaling of divertor power footprint width in RF-heated type-III ELMy H-mode on the EAST superconducting tokamak
L. Wang et al.
NUCLEAR FUSION (2014)
Inboard and outboard radial electric field wells in the H- and I-mode pedestal of Alcator C-Mod and poloidal variations of impurity temperature
C. Theiler et al.
NUCLEAR FUSION (2014)
Consequences of a reduction of the upstream power SOL width in ITER
A. S. Kukushkin et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
The role of drifts in the plasma transport at the tokamak core-SOL interface
A. V. Chankin et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Six-field two-fluid simulations of peeling-ballooning modes using BOUT plus
T. Y. Xia et al.
NUCLEAR FUSION (2013)
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
T. Eich et al.
NUCLEAR FUSION (2013)
Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks
R. J. Goldston
NUCLEAR FUSION (2012)
Analysis of a multi-machine database on divertor heat fluxes
M. A. Makowski et al.
PHYSICS OF PLASMAS (2012)
Surface thermocouples for measurement of pulsed heat flux in the divertor of the Alcator C-Mod tokamak
D. Brunner et al.
REVIEW OF SCIENTIFIC INSTRUMENTS (2012)
Multi-parameter scaling of divertor power load profiles in D, H and He plasmas on JET and implications for ITER
W. Fundamenski et al.
NUCLEAR FUSION (2011)
Nonlinear ELM simulations based on a nonideal peeling-ballooning model using the BOUT plus plus code
X. Q. Xu et al.
NUCLEAR FUSION (2011)
Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model
T. Eich et al.
PHYSICAL REVIEW LETTERS (2011)
Scaling of the power exhaust channel in Alcator C-Mod
B. LaBombard et al.
PHYSICS OF PLASMAS (2011)
Divertor IR thermography on Alcator C-Mod
J. L. Terry et al.
REVIEW OF SCIENTIFIC INSTRUMENTS (2010)
BOUT++: A framework for parallel plasma fluid simulations
B. D. Dudson et al.
COMPUTER PHYSICS COMMUNICATIONS (2009)
Status and verification of edge plasma turbulence code BOUT
M. V. Umansky et al.
COMPUTER PHYSICS COMMUNICATIONS (2009)
Edge radial electric field structure and its connections to H-mode confinement in Alcator C-Mod plasmas
R. M. McDermott et al.
PHYSICS OF PLASMAS (2009)
Edge profile stiffness and insensitivity of the density pedestal to neutral fuelling in Alcator C-Mod edge transport barriers
J. W. Hughes et al.
NUCLEAR FUSION (2007)
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment
R. Maingi et al.
JOURNAL OF NUCLEAR MATERIALS (2007)
Chapter 4: Power and particle control
A. Loarte et al.
NUCLEAR FUSION (2007)
Numerical study of neoclassical plasma pedestal in a tokamak geometry
CS Chang et al.
PHYSICS OF PLASMAS (2004)
Drift-ordered fluid equations for field-aligned modes in low-beta collisional plasma with equilibrium pressure pedestals
AN Simakov et al.
PHYSICS OF PLASMAS (2003)
Observations and empirical scalings of the high-confinement mode pedestal on Alcator C-Mod
JW Hughes et al.
PHYSICS OF PLASMAS (2002)
Low-to-high confinement transition simulations in divertor geometry
XQ Xu et al.
PHYSICS OF PLASMAS (2000)