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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…
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Keywords:
sio2 reaction;
sodium;
reaction;
sodium cooled ... See more keywords
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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…
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Keywords:
cycle;
sodium cooled;
conversion system;
system ... See more keywords
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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…
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Keywords:
thorium;
fuel;
fast reactor;
cooled fast ... See more keywords
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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…
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Keywords:
hendl data;
benchmarking hendl;
data library;
sodium cooled ... See more keywords
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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…
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Keywords:
full core;
cooled fast;
sodium cooled;
pin cell ... See more keywords
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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…
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Keywords:
cooled fast;
sodium cooled;
pump;
reactor thermal ... See more keywords
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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.…
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Keywords:
model;
application model;
fast reactor;
sodium cooled ... See more keywords
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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…
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Keywords:
detection;
heat exchanger;
sodium;
cooled fast ... See more keywords
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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…
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Keywords:
cooled fast;
sodium cooled;
tritium effluent;
fast reactor ... See more keywords
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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…
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Keywords:
outlet sodium;
cooled fast;
sodium cooled;
sodium ... See more keywords
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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…
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Keywords:
optimization;
sodium cooled;
cask;
fuel ... See more keywords