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Journal ArticleDOI

Conceptual design activities of FDS series fusion power plants in China

Yican Wu
- 01 Nov 2006 - 
- Vol. 81, Iss: 23, pp 2713-2718
TLDR
A series of fusion power plants (named FDS series) have been designed and assessed for the examination of the feasibility and the safety, environmental and economical potential of fusion with emphasizing the blanket design optimization on neutronics, thermal-hydraulics, electro-magnetics, material, structural performance analyses in China as discussed by the authors.
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This article is published in Fusion Engineering and Design.The article was published on 2006-11-01. It has received 260 citations till now. The article focuses on the topics: Blanket.

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Citations
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Journal ArticleDOI

CAD-based interface programs for fusion neutron transport simulation

TL;DR: The main functions of the three interface programs are introduced and a benchmark test based on the ITER model is presented.
Journal ArticleDOI

Progress in development of China Low Activation Martensitic steel for fusion application

TL;DR: A series of R&D activities on the structural material China Low Activation Martensitic steel (CLAM) and related blanket technology are being carried out in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) as mentioned in this paper.
Journal ArticleDOI

Design status and development strategy of China liquid lithium-lead blankets and related material technology

TL;DR: A series of liquid lithium lead blankets have been designed and assessed in China, with four types of liquid lead blankets including the RAFM steel-structured He-cooled quasi-static LiPb tritium breeder (SLL) blanket.
Journal ArticleDOI

Conceptual design and testing strategy of a dual functional lithium–lead test blanket module in ITER and EAST

Yican Wu
- 19 Oct 2007 - 
TL;DR: In this paper, a dual functional lithium-lead (DFLL) test blanket module (TBM) concept has been proposed for testing in the International Thermonuclear Experimental Reactor (ITER) and the Experimental Advanced Superconducting Tokamak (EAST) in China to demonstrate the technologies of the liquid lithium−lead breeder blankets with emphasis on the balance between the risks and the potential attractiveness of blanket technology development.
Journal ArticleDOI

Conceptual design of the China fusion power plant FDS-II

TL;DR: An overview of the FDS-II conceptual design will be presented, a series of performance analyses are summarized and further R&D needs are specified.
References
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Journal ArticleDOI

Features of spherical torus plasmas

TL;DR: The spherical torus is a very small aspect ratio (A 2 ) characterized by high toroidal beta (βt > 0.2), low poloidal β (βp 1.5), and strong magnetic helical pitch (Θ comparable to F).
Journal ArticleDOI

Progress in development of China Low Activation Martensitic steel for fusion application

TL;DR: A series of R&D activities on the structural material China Low Activation Martensitic steel (CLAM) and related blanket technology are being carried out in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) as mentioned in this paper.
Journal ArticleDOI

Conceptual design of the fusion-driven subcritical system FDS-I

TL;DR: In this article, a conceptual design of the FDS-I is presented, which consists of the fusion neutron driver with relatively easy-achieved plasma parameters, and the He-gas/liquid lithium-lead Dual-cooled subcritical Waste Transmutation (DWT) blanket used to transmute long-lived radioactive wastes and to generate energy on the basis of self-sustainable fission and fusion fuel cycle.
Journal ArticleDOI

The fusion-driven hybrid system and its material selection

TL;DR: The fusion-driven multi-functional hybrid reactor system (FDS) is proposed as a middle step toward the final application of fusion energy and its strategic goal and roadmap is addressed along with its potential advantages.
Journal ArticleDOI

Spherical torus concept as power plants—the ARIES-ST study

TL;DR: The ARIES-ST study was undertaken as a national US effort to investigate the potential of the spherical tokamak concept as a fusion power plant as discussed by the authors, which has an aspect ratio of 1.6, a major radius of 3.2 m and triangularity of 0.64.
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