The critical issue of divertor configuration for heat and particle flux control in a conceptual ARIES compact stellarator (CS) reactor is addressed. The goal is to de-termine a divertor location and geometry with a peak heat load of not more than 10 MW/m2 for a CS equilib-rium based on the configuration to be used in the NCSX experiment, optimized for high beta (6.4%) and designed for low alpha-particle power loss fraction (5%). The surface heat flux on the target has three components: thermal particles, lost energetic alphas, and radiation from the core and the scrape-off layer. The first two com-ponents are dominant and their magnitudes can be com-parable. To maintain a tritium-breeding ratio of 1.1, the total target area should not excee...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
As the new research plan of Plasma Research Center of the University of Tsukuba, we are planning to ...
The ARIES-CS project was a multi-year multi-institutional project to assess the feasibility of a com...
Novel stellarator configurations have been developed for ARIES-CS. These configurations are optimize...
Novel stellarator configurations have been devel-oped for ARIES-CS. These configurations are optimiz...
The ARIES-RS divertor system is selected and analyzed. A radiative divertor approach using Ne as the...
An integrated study of compact stellarator power plants, ARIES-CS, has been conducted to explore att...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
The spherical tokamak (ST) regime of low-aspect-ratio (LAR) tokamak operation has provided an opport...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
Over the past 2-3 decades, stellarator power plants have been studied in the U.S., Europe, and Japan...
The ARIES-CS team has concluded an integrated study of a compact stellarator power plant, involving ...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
The 3D effects on divertor heat loads have been investigated for performance-optimized island divert...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
As the new research plan of Plasma Research Center of the University of Tsukuba, we are planning to ...
The ARIES-CS project was a multi-year multi-institutional project to assess the feasibility of a com...
Novel stellarator configurations have been developed for ARIES-CS. These configurations are optimize...
Novel stellarator configurations have been devel-oped for ARIES-CS. These configurations are optimiz...
The ARIES-RS divertor system is selected and analyzed. A radiative divertor approach using Ne as the...
An integrated study of compact stellarator power plants, ARIES-CS, has been conducted to explore att...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
The spherical tokamak (ST) regime of low-aspect-ratio (LAR) tokamak operation has provided an opport...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
Over the past 2-3 decades, stellarator power plants have been studied in the U.S., Europe, and Japan...
The ARIES-CS team has concluded an integrated study of a compact stellarator power plant, involving ...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
The 3D effects on divertor heat loads have been investigated for performance-optimized island divert...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
The divertor concept and the divertor materials envisaged for ITER FEAT restrict the maximum values ...
As the new research plan of Plasma Research Center of the University of Tsukuba, we are planning to ...