Articles with "sodium cooled" as a keyword



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Thermal behavior of sodium hydroxide–structural concrete composition of sodium-cooled fast reactor

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Published in 2017 at "Journal of Thermal Analysis and Calorimetry"

DOI: 10.1007/s10973-017-6236-1

Abstract: Under postulated accidental condition of sodium-cooled fast reactor (SFR), liquid sodium spill into the floor may lead to fail the steel liner. Consequently, sodium–concrete reaction (SCR) comes to occur by direct contact of liquid sodium… read more here.

Keywords: sio2 reaction; sodium; reaction; sodium cooled ... See more keywords
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Preliminary design of an SCO2 conversion system applied to the sodium cooled fast reactor

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Published in 2021 at "Frontiers in Energy"

DOI: 10.1007/s11708-021-0777-5

Abstract: The supercritical carbon dioxide (SCO2) Brayton cycle has become an ideal power conversion system for sodium-cooled fast reactors (SFR) due to its high efficiency, compactness, and avoidance of sodium-water reaction. In this paper, the 1200… read more here.

Keywords: cycle; sodium cooled; conversion system; system ... See more keywords
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Investigation on the potential use of thorium as fuel for the Sodium-cooled Fast Reactor

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Published in 2017 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2017.01.030

Abstract: Generation IV reactors are planned to be an evolutionary step in the history of nuclear power plants. Although they have many advantageous properties, five of the six concepts are designed for the utilization of uranium–plutonium… read more here.

Keywords: thorium; fuel; fast reactor; cooled fast ... See more keywords
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Benchmarking the HENDL-3.0 data library by simulating a sodium-cooled test reactor

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Published in 2018 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2018.08.040

Abstract: Abstract Advanced computation to deal with sophisticated nuclear systems and their process mainly relies on competent nuclear data libraries. The library could significantly alter the simulation results. In this study, the competence of a Hybrid… read more here.

Keywords: hendl data; benchmarking hendl; data library; sodium cooled ... See more keywords
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Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core

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Published in 2019 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2019.01.033

Abstract: Abstract To quantify the uncertainties in the neutronics calculations of sodium-cooled fast reactor (SFR), a series of sensitivity and uncertainty (S&U) analysis were performed on two typical SFRs, which were a large-size MOX-fueled core and… read more here.

Keywords: full core; cooled fast; sodium cooled; pin cell ... See more keywords
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Performance analysis of magnetohydrodynamic pump for sodium-cooled fast reactor thermal hydraulic experiment

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Published in 2019 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2019.04.037

Abstract: Abstract An MHD pump with a developed pressure of 4 bar and flow rate of 20 kg/s was designed using electrical equivalent circuit method, which is typically used in analyzing linear induction machines. The experiment is conducted… read more here.

Keywords: cooled fast; sodium cooled; pump; reactor thermal ... See more keywords
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Application of a 3D model in the transient system analysis of sodium-cooled fast reactor

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Published in 2020 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2019.106967

Abstract: Abstract In this study, the application of a 3D model for the sodium pool of the sodium-cooled fast reactor was realized. The basic equations and numerical solution methods of the model were given in detail.… read more here.

Keywords: model; application model; fast reactor; sodium cooled ... See more keywords
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Reliable leak detection in a heat exchanger of a sodium-cooled fast reactor

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Published in 2020 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2020.107357

Abstract: Abstract The heat exchanger (HE) should be permanently monitored in order to detect water or nitrogen leaking into a sodium circuit, which can affect the sodium-cooled fast reactor (SFR) performance or safety. The HE must… read more here.

Keywords: detection; heat exchanger; sodium; cooled fast ... See more keywords
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Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor

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Published in 2021 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2021.108334

Abstract: Abstract A tritium transport model for a pool-type sodium cooled fast reactor was developed for estimation of tritium effluents from the Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR). For this purpose, the transport model developed… read more here.

Keywords: cooled fast; sodium cooled; tritium effluent; fast reactor ... See more keywords
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Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)

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Published in 2021 at "Annals of Nuclear Energy"

DOI: 10.1016/j.anucene.2021.108347

Abstract: Abstract It is a critical safety issue of thermal fatigue in the core outlet of sodium cooled fast reactors (SFRs) due to the mixing phenomenon of coolant with different temperatures flowing from different assemblies. In… read more here.

Keywords: outlet sodium; cooled fast; sodium cooled; sodium ... See more keywords
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On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

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Published in 2019 at "Nuclear Engineering and Technology"

DOI: 10.1016/j.net.2018.09.007

Abstract: Abstract For the continuous operation of a nuclear reactor, burnt fuel needs to be replaced with fresh fuel, where appropriate (ex-vessel) fuel handling is required. Particularly for the Sodium-cooled Fast Reactor (SFR) refueling, its process… read more here.

Keywords: optimization; sodium cooled; cask; fuel ... See more keywords