In SIII-D, good H-mode confinement has been obtained with up to 6 MW of neutral-beam injection (NBI). In this report we summarize the essential features of divertor operation for DIII-D H-mode plasma. Briefly, our measurements show that: Large edge density and temperarture gradients are obtained with scale lengths of a few cm at the midplane; In the steady state, approximately 10-20% of the input power is deposited on the divertor plates in a region that is peaked on the separatrix and extends radially over )approx equal) 2-4 cm at the outboard intercept. More power (2:1) reaches the outboard intercept than the inboard; Low electron temperature (less than or equal to20eV) and high density (n/sub e//sup div/ )approx equal) n/sub e//sup main/...
The DIII-D national fusion research program focuses on establishing the scientific basis for optimiz...
The goals of DIII-D advanced tokamak (AT) experiments are investigation and optimization of the uppe...
A series of experiments was conducted on the DIII-D tokamak to investigate the physical processes wh...
In this paper we present an overview of the results and conclusions of our most recent divertor phys...
The DIII-D research program is aimed at developing the scientific basis for advanced modes of operat...
The authors' data indicate that the L-mode to H-mode transition in the DIII-D tokamak is associated ...
Improvements to the DIII-D tokamak have led to significant new research results and enhanced perform...
Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (D...
The DIII-D program focuses on developing fusion physics in an integrated program of tokamak concept ...
We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DI...
Recent results from the DIII-D tokamak have provided significant contributions to the understanding ...
DIII-D is making significant contributions to a scientific basis for sustained burning plasma operat...
Excessive thermal power loading on the divertor structures presents a design difficulty for future-g...
The H-mode confinement scenario presents a method to achieve higher fusion power density and hence l...
A comprehensive set of experiments has been carried out on the DIII-D tokamak to measure the 2-D (R,...
The DIII-D national fusion research program focuses on establishing the scientific basis for optimiz...
The goals of DIII-D advanced tokamak (AT) experiments are investigation and optimization of the uppe...
A series of experiments was conducted on the DIII-D tokamak to investigate the physical processes wh...
In this paper we present an overview of the results and conclusions of our most recent divertor phys...
The DIII-D research program is aimed at developing the scientific basis for advanced modes of operat...
The authors' data indicate that the L-mode to H-mode transition in the DIII-D tokamak is associated ...
Improvements to the DIII-D tokamak have led to significant new research results and enhanced perform...
Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (D...
The DIII-D program focuses on developing fusion physics in an integrated program of tokamak concept ...
We summarize results from DIII-D in regard to issues for reactor application of H-mode. Recently, DI...
Recent results from the DIII-D tokamak have provided significant contributions to the understanding ...
DIII-D is making significant contributions to a scientific basis for sustained burning plasma operat...
Excessive thermal power loading on the divertor structures presents a design difficulty for future-g...
The H-mode confinement scenario presents a method to achieve higher fusion power density and hence l...
A comprehensive set of experiments has been carried out on the DIII-D tokamak to measure the 2-D (R,...
The DIII-D national fusion research program focuses on establishing the scientific basis for optimiz...
The goals of DIII-D advanced tokamak (AT) experiments are investigation and optimization of the uppe...
A series of experiments was conducted on the DIII-D tokamak to investigate the physical processes wh...