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Lead-cooled system design and challenges in the frame of Generation IV International Forum
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TLDR
An overview of the historical development of the LFR, a summary of the advantages and challenges associated with heavy liquid metal coolants, and an update of the current status of development of LFR concepts under consideration are provided.About:
This article is published in Journal of Nuclear Materials.The article was published on 2011-08-31. It has received 62 citations till now.read more
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Generation IV nuclear reactors: current status and future prospects
TL;DR: In this paper, the authors present the state-of-the-art for GEN IV NPPs technologies (VHTR, SFR, SCWR, GFR, LFR and MSR) providing a comprehensive literature review of different designs, discussing the major R&D challenges and comparing them with other advanced technologies available for the middle and long-term energy market.
Journal ArticleDOI
Corrosion behavior of cold-worked austenitic stainless steels in liquid lead–bismuth eutectic
TL;DR: In this article, the effect of cold working on the corrosion behavior of austenitic stainless steels in liquid lead-bismuth eutectic (LBE) was studied to develop accelerator-driven systems for the transmutation of long-lived radioactive wastes and lead bismuth cooled fast reactors.
Journal ArticleDOI
Corrosion behavior of austenitic steels in liquid lead bismuth containing 10−6 wt% and 10−8 wt% oxygen at 400–500 °C
TL;DR: In this article, three austenitic steels (316L, DIN 1.4970 tube and rod material) were tested up to 5000h at temperatures between 400 and 500°C in PbBi containing 10 −8 Âwt% oxygen.
Journal ArticleDOI
Corrosion behavior of Si-enriched steels for nuclear applications in liquid lead–bismuth
TL;DR: In this article, the corrosion behavior of Si-enriched steels in liquid lead-bismuth was studied in order to develop accelerator driven systems for transmutation of long-lived radioactive wastes and lead bismuth cooled fast reactors.
The Lead Fast Reactor: Demonstrator (ALFRED) and ELFR Design
A. Alemberti,M. Frogheri +1 more
TL;DR: In this paper, a deep analysis of previous design as generated by the previous ELSY project, in order to reach an improved European Lead Fast Reactor, ELFR configuration, is presented.
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SSTAR: The US lead-cooled fast reactor (LFR)
TL;DR: This paper presents the motivation for development of internationally deployable nuclear energy systems as well as a summary of one such system, SSTAR, which is the US Generation IV lead-cooled fast reactor system.
The ELSY Project
Cinotti Luciano,Locatelli Giuliano,Aït Abderrahim H,Monti Stefano,Benamati Gianluca,Tucek Kamil,Struwe Dankward,Orden Alfredo,Corsini Giovanni,Lecarpentier D +9 more
Lead-cooled fast reactor (lfr) overview and perspectives
TL;DR: The lead-cooled fast Reactor (LFR) as discussed by the authors was proposed as a technology with great potential to meet the small-unit electricity needs of remote sites while also offering advantages as a large system for grid-connected power stations.