Journal ArticleDOI
Blanket Comparison and Selection Study
John W. Davis,T. A. Lechtenberg,Dale L. Smith,F.W. Wiffen,Saurin Majumdar,Omesh K. Chopra,Peter F. Tortorelli,Jackson H. De Van,Dai-Kai Sze,Yung Y. Liu,Michael C. Billone,Albert K. Fischer,S.W. Tam,R.G. Clemmer,Glenn W. Hollenberg,Ahmed Hassanein,S.J. Piet,C.P.C. Wong,William D. Bjorndahl,J. Jung,John V. Foley,Yousry Gohar,S. Yang +22 more
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This article is published in Fusion Technology.The article was published on 1985-09-01. It has received 108 citations till now. The article focuses on the topics: Selection (genetic algorithm) & Blanket.read more
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Present understanding of MHD and heat transfer phenomena for liquid metal blankets
TL;DR: A review of experimental work on magnetohydrodynamic (MHD) and heat transfer (HT) characteristics of liquid metal flows in fusion relevant conditions is presented in this paper, where experiments on MHD flow pressure drop in straight channels of round and rectangular cross-section with electroconducting walls in a transverse magnetic field show good agreement with theoretical predictions, and simple engineering formulas are confirmed.
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Ceramic breeder materials
TL;DR: In this paper, a comparison of ceramic properties for use in a tritium breeding blanket is presented, aiming at the identification of the most promising material to use in the breeding blanket.
Journal ArticleDOI
Development of the lead lithium (dcll) blanket concept
TL;DR: In this paper, the authors proposed dual coolant blankets with helium cooled FW/blanket structure and a self-cooled breeding zone, with electrical insulation by ceramic-coatings or sandwich flow channel inserts.
Journal ArticleDOI
Tritium recovery from liquid metals
TL;DR: In this paper, the authors reviewed recent work on tritium recovery from pure lithium and Pb-17Li alloy and discussed the implications of the work for successful future development.
Journal ArticleDOI
Design and development of the Flibe blanket for helical-type fusion reactor FFHR
Akio Sagara,H. Yamanishi,Shinsaku Imagawa,Takeo Muroga,T. Uda,Tetsuji Noda,Satoru Takahashi,Ken-ichi Fukumoto,T. Yamamoto,Hideki Matsui,Akira Kohyama,H. Hasizume,Saburo Toda,Akihiko Shimizu,Atsushi Suzuki,Y. Hosoya,Tanaka Satoru,T. Terai,Dai-Kai Sze,O. Motojima +19 more
TL;DR: In this article, a localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR).