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Journal ArticleDOI

Improved tokamak concept focusing on easy maintenance

TLDR
In this paper, a torus system is radially divided into equal sectors and each sector forms an assembly unit, all the piping and feeder systems are extracted to the spacious torus central region.
About
This article is published in Fusion Engineering and Design.The article was published on 1998-09-01. It has received 66 citations till now. The article focuses on the topics: Magnetic confinement fusion & Tokamak.

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Citations
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Current status and critical issues for development of SiC composites for fusion applications

TL;DR: In this paper, the authors review the development, characterization, and irradiation effect studies for SiC composites for fusion energy applications and make the case that SiC composite are progressing from the stage of potential viability and proof-of-principle to one where they are ready for system demonstration, i.e., for flow channel inserts in Pb-Li blankets.
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Current status and recent research achievements in SiC/SiC composites

TL;DR: The silicon carbide fiber-reinforced SiC/SiC composite system for fusion applications has seen a continual evolution from development a fundamental understanding of the material system and its behavior in a hostile irradiation environment to the current effort which is directed at a broad-based program of technology maturation program as mentioned in this paper.
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Silicon carbide composites as fusion power reactor structural materials

TL;DR: The recent progress in the understanding and of basic phenomenon related to the use of SiC and SiC composite in fusion applications will be presented in this article, including both fundamental radiation effects in SiC, and engineering issues such as joining and general materials properties.
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Design and material issues for high performance SiCf/SiC-based fusion power cores

TL;DR: The SiCf/SiC composite is a promising structural material candidate for fusion power cores and has been considered internationally in several power plant studies as discussed by the authors, but its behavior and performance at high temperatures and under irradiation are still not well known and need to be better characterized.
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Radiation-tolerant joining technologies for silicon carbide ceramics and composites

TL;DR: In this paper, a standardized methodology for carrying out joint testing has been established consistent with the small volume samples mandated by neutron irradiation testing, and significant progress made towards identifying and processing irradiation-tolerant joining methods for nuclear-grade SiC.
References
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Journal ArticleDOI

Neoclassical transport of impurities in tokamak plasmas

TL;DR: In this paper, a closed set of moment equations is presented for the time evolution of thermodynamic and magnetic field quantities which results from collisional transport of the plasma and two-dimensional motion of the magnetic flux surface geometry.
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Status and prospects for SiCSiC composite materials development for fusion applications

TL;DR: In this paper, the effect of neutron irradiation on the properties of SiC-SiC composite between 500 and 1200 °C is discussed and ongoing research and development efforts show extremely promising properties and behavior for SiCSiC composites for fusion applications.
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Study of a compact reversed shear Tokamak reactor

TL;DR: In this article, the Compact Reversed Shear Tokamak, CREST-1, is designed with a moderate aspect ratio (R/a = 3.4), which will allow us to experimentally develop this CREST concept by ITER.
Journal Article

Study of critical beta non-circular tokamak equilibria sustained in steady state by beam driven currents

TL;DR: In this paper, a new code for MHD equilibrium/current drive analysis has been developed which can be used in an analysis of high beta tokamak equilibria consistent with beam driven current profiles.
Journal ArticleDOI

Critical beta non-circular tokamak equilibria sustained in steady state by beam driven currents

TL;DR: In this article, a new code for MHD equilibrium/current drive analysis has been developed which can be used in an analysis of high beta tokamak equilibria consistent with beam driven current profiles.
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