Journal ArticleDOI
A Road Map for the Realization of Global-scale Thorium Breeding Fuel Cycle by Single Molten-Fluoride Flow
Kazuo Furukawa,Kazuto Arakawa,L. Berrin Erbay,Yasuhiko Ito,Yoshio Kato,H. Kiyavitskaya,Alfred Lecocq,Koshi Mitachi,Ralph Moir,Hiroo Numata,J. Paul Pleasant,Yuzuru Sato,Yoichiro Shimazu,Vadim A. Simonenco,Din Dayal Sood,Carlos Urban,Ritsuo Yoshioka +16 more
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TLDR
The Thorium Molten Salt Nuclear Energy Synergetic System [THORIMS-NES] as mentioned in this paper is a symbiotic system, based on the thorium-uranium-233 cycle.About:
This article is published in Energy Conversion and Management.The article was published on 2008-07-01. It has received 101 citations till now. The article focuses on the topics: Thorium fuel cycle & Fissile material.read more
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Journal ArticleDOI
The molten salt reactor (MSR) in generation IV: Overview and perspectives
Jérôme Serp,M. Allibert,Ondřej Beneš,Sylvie Delpech,O. Feynberg,V. Ghetta,Daniel Heuer,David Eugene Holcomb,Victor Ignatiev,Jan Leen Kloosterman,Lelio Luzzi,Elsa Merle-Lucotte,Jan Uhlíř,Ritsuo Yoshioka,Dai Zhi-Min +14 more
TL;DR: An overview of the international efforts on these reactor types carried out in the framework of Generation-IV can be found in this article, where the authors give an overview of international R&D efforts.
The Molten Salt Reactor in Generation IV: Overview and Perspectives
H. Boussier,Sylvie Delpech,V. Ghetta,D. Heuer,D. E. Holcomb,Victor Ignatiev,E. Merle Lucotte,J. Serp +7 more
Journal ArticleDOI
Molten salt reactors: A new beginning for an old idea
TL;DR: In this article, it is shown that a simple yet crucial modification to core geometry can solve this problem and enable the many advantages of the two-fluid design, which is a major potential change to the traditional Single Fluid, MSBR design and a subject of this presentation is a return to the mode of operation that ORNL proposed for the majority of its MSR program.
Journal ArticleDOI
Viability of thorium-based nuclear fuel cycle for the next generation nuclear reactor: Issues and prospects
TL;DR: A review on the past, present and the future of thorium fuel cycle is presented in this paper, looking at the prospects and drawbacks on the possibility of using thorium-based nuclear fuel for commercial reactors realising the increasing challenges of UF.
Journal ArticleDOI
Responsible mineral and energy futures: views at the nexus
Damien Giurco,Benjamin McLellan,Benjamin McLellan,Daniel M. Franks,Keisuke Nansai,Tim Prior,Tim Prior +6 more
TL;DR: In this paper, the authors focus on the current forces for change in the minerals industry: community drivers regarding social licence to operate, new technologies and consumer and government drivers on responsible minerals, and propose a research agenda for an expanded notion of responsible minerals which recognises the complexity of the mineral-energy nexus and connects it to progressing sustainable futures.
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Journal ArticleDOI
HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design — Final Report
Ralph W. Moir,R. L. Bieri,Xiang M. Chen,T. J. Dolan,M. A. Hoffman,P.A. House,R. L. Leber,J. D. Lee,Y. T. Lee,J. C. Liu,G. R. Longhurst,Wayne R. Meier,P. F. Peterson,Ronald W. Petzoldt,V. E. Schrock,M. Tobin,W. H. Williams +16 more
TL;DR: In this article, the liquid-wall HYLIFE-II conceptual design has been presented, which has been shown to reduce the electricity cost by using a neutronically thick array of flowing molten-salt jets, which will not burn, has a low tritium solubility and inventory, and protects the chamber walls.
Journal ArticleDOI
The Molten Salt Reactor Adventure
TL;DR: A personal history of the development of molten salt reactors in the United States is presented in this article, where the initial goal was an aircraft propulsion reactor, and a molten fluoride-fueled Aircraft Reactor E...
ReportDOI
Conceptual design characteristics of a denatured molten-salt reactor with once-through fueling
TL;DR: In this article, the conceptual feasibility of a molten-salt power reactor fueled with denatured /sup 235/U and operated with a minimum of chemical processing was examined and a conceptual core design was developed in which the power density was low enough to allow a 30-year life expectancy of the moderator graphite with a fluence limit of 3 x 10/sup 26/ neutrons/m/sup 2/ (E > 50 keV).