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Journal ArticleDOI

ALFRED reactor coolant system design

TLDR
In this article, the configuration of the ALFRED reactor coolant system showing its present state of development and technological innovations is presented, and the current plant architecture provides for a thermal power up to 300 MWth and a coolant temperature range from a minimum of 390°C to a maximum of 520°C.
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This article is published in Nuclear Engineering and Design.The article was published on 2020-12-15. It has received 21 citations till now. The article focuses on the topics: Generation IV reactor & Small modular reactor.

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Citations
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Honeycomb structure with oxygen-poor pores at the top of magnetite layer on a martensitic steel CLAM exposed to lead-bismuth eutectic at 500 ºC

TL;DR: In this article , a model based on the local dissolution of magnetite crystals was proposed to explain the formation process of honeycomb structures, which can lead to much oxygen loss in the spinel layer, which may induce pitting corrosion and promote its development.
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Improvements of RELAP5/Mod3.3 heat transfer capabilities for simulation of in-pool passive power removal systems

TL;DR: In this article, a modified version of RELAP5/Mod3.3 has been developed to handle fundamental heat exchange phenomena involved in passive in-pool safety systems, such as pool boiling and film condensation.
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On the use of advanced nuclear cogeneration plant integrated into latent heat storage for district heating

TL;DR: In this article , thermal storage modules with two separate heat transfer fluids (HTFs) are presented, in which several cylindrical tubes of phase change material (PCM) are vertically located.
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Liquid lead Flow-accelerated corrosion testing with the Rotating Cage set-up: A CFD optimisation

TL;DR: In this paper, the rotating cage setup, a simple laboratory methodology extensively used for flow-accelerated corrosion and erosion-corrosion testing, is optimized via CFD simulations for flow accelerated corrosion testing with liquid lead for lead-cooled nuclear reactors.
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Liquid lead flow-accelerated corrosion testing with the rotating cage set-up: A CFD optimisation

TL;DR: In this article , the rotating cage setup, a simple laboratory methodology extensively used for flow accelerated corrosion and erosion-corrosion testing, is optimized via CFD simulations for flow-accelerated corrosion testing with liquid lead for lead-cooled nuclear reactors.
References
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Review of the studies on fundamental issues in LBE corrosion

TL;DR: In this article, the current understanding of corrosion and the fundamental issues relevant to corrosion when using lead bismuth eutectic (LBE) as a heavy liquid metal nuclear coolant are reviewed.
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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.
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European lead fast reactor—ELSY

TL;DR: The European Lead Fast Reactor (ELSY) as discussed by the authors is a 600 mWe pool-type reactor cooled by pure lead, which has been developed starting from September 2006, in the frame of the EU-FP6-ELSY project.
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Corrosion and radiation resistant nanoceramic coatings for lead fast reactors

TL;DR: In this paper, the results show that the coatings retain structural integrity under the conditions investigated, which is a crucial prerogative for corrosion protection with ceramic coatings, and they also show that corrosion is not observed in either pristine (4000h) or irradiated (1000h) coated samples.
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SVBR-100 module-type fast reactor of the IV generation for regional power industry

TL;DR: In this paper, basic conceptual provisions of the innovative nuclear power technology (NPT) based on modular fast reactors (FR) SVBR-100, summarized results of calculations of the reactor, analysis of the opportunities of multi-purpose application of such reactor facilities (RF) including export potentials with due account of nonproliferation requirements.
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