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Journal ArticleDOI

ARIES-ST breeding blanket design and analysis

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TLDR
The ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio "spherical torus" (ST) plasma as discussed by the authors, which uses an advanced breeding blanket with flowing PbLi breeder and He-cooled ferritic steel structures.
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This article is published in Fusion Engineering and Design.The article was published on 2000-11-01. It has received 37 citations till now. The article focuses on the topics: Blanket.

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Citations
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Journal ArticleDOI

Characterization of key magnetohydrodynamic phenomena in PbLi flows for the US DCLL blanket

TL;DR: The dual-coolant lead-lithium (DCLL) blanket concept is considered in the US for testing in ITER and as a candidate for using in DEMO reactor.
Journal ArticleDOI

Code development for analysis of MHD pressure drop reduction in a liquid metal blanket using insulation technique based on a fully developed flow model

TL;DR: In this article, a numerical code for analysis of a fully developed MHD flow in a channel of a liquid metal blanket using various insulation techniques is presented, which includes a finite-volume formulation, automatically generated Hartmann number sensitive meshes, and effective convergence acceleration technique.
Journal ArticleDOI

Magnetohydrodynamic and Thermal Issues of the SiCf/SiC Flow Channel Insert

TL;DR: In the dual-coolant lead lithium (DCLL) blanket, the key element is the flow channel insert (FCI) made of a silicon carbide composite (SiCf/SiC), which serves as electric and thermal insulator.
Journal ArticleDOI

U.S. Plans and Strategy for ITER Blanket Testing

TL;DR: In this paper, a study was initiated to select the two blanket options for the US ITER-TBM in light of new R and D results from the US and world programs over the past decade.
Journal ArticleDOI

Reduced-activation bainitic and martensitic steels for nuclear fusion applications

TL;DR: Reduced activation steels were developed to enhance safety and reduce adverse environmental effects of future fusion power plants as discussed by the authors, and the feasibility of their use for fusion was investigated in an international collaboration from 1994 to present.
References
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Development of oxide dispersion strengthened ferritic steels for fusion

TL;DR: In this article, an oxide dispersion strengthened (ODS) ferritic steel with high temperature strength has been developed in line with low activation criteria for application in fusion power systems and the composition Fe−13.5Cr−2W−0.25Y2O3 was chosen to provide a minimum chromium content to insure fully delta-ferrite stability.
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R&D of oxide dispersion strengthened ferritic martensitic steels for FBR

TL;DR: In this article, the authors developed oxide dispersion strengthened (ODS) ferritic/martensitic steels for the long-life core of a Fast Breeder Reactor (FBR).
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Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system

TL;DR: In this paper, a self-cooled liquid metal breeder blanket with a closed cycle helium gas turbine was proposed to eliminate the potential for liquid metal-water reactions by replacing the Rankine cycle with a Brayton cycle.
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