Homogenous Transmutation of 237Np, 241Am, 243Am in a Lead-Cooled Fast Reactor
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DOI: 10.1007/s10512-021-00756-1
Abstract: The results of a study of the effect of the homogeneous addition of 237Np, 241Am, 243Am into the fuel on the neutronics characteristics of a lead-cooled fast reactor are reported. The reasons for the change… read more here.
Keywords: 241am 243am; fast reactor; cooled fast; 237np 241am ... See more keywords
Investigation on the potential use of thorium as fuel for the Sodium-cooled Fast Reactor
Sign Up to like & getrecommendations! 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
Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core
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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
Performance analysis of magnetohydrodynamic pump for sodium-cooled fast reactor thermal hydraulic experiment
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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
Reliable leak detection in a heat exchanger of a sodium-cooled fast reactor
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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
A multiphysics simulation suite for liquid metal-cooled fast reactors
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DOI: 10.1016/j.anucene.2021.108213
Abstract: Abstract A new multiphysics simulation suite has been created to model Liquid Metal-cooled Fast Reactors (LMFRs). LUPINE : “LMFR Utility for Physics Informed Nuclear Engineering” is based on the Finite Element Method (FEM) and employs… read more here.
Keywords: fast reactors; multiphysics simulation; metal cooled; cooled fast ... See more keywords
Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor
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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
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)
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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
Development of a sub-channel thermal hydraulic analysis code and its application to lead cooled fast reactor
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DOI: 10.1016/j.applthermaleng.2017.02.044
Abstract: Abstract The most important candidate for 4th generation nuclear system is lead or lead alloy cooled fast reactor. In the design phase of a lead cooled reactor, it is a top priority to finish the… read more here.
Keywords: code; analysis; fast reactor; cooled fast ... See more keywords
Numerical study on thermal deformation behaviors of the single subassembly in sodium-cooled fast reactors based on Euler-Bernoulli beam theory
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DOI: 10.1016/j.nucengdes.2019.01.027
Abstract: Abstract Due to the special geometry and compact arrangement of subassemblies in the sodium-cooled fast reactor, thermal deformation of the assemblies are easily triggered by uneven temperature distribution in the reactor core, which is negative… read more here.
Keywords: thermal deformation; cooled fast; sodium cooled; deformation behaviors ... See more keywords
Numerical modelling of cover gas thermal hydraulics in Sodium-cooled Fast Reactors
Sign Up to like & getrecommendations! Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110347
Abstract: Abstract An argon gas cover layer is usually used in Sodium-cooled Fast Reactors (SFR) above the pool of sodium to prevent leakage of air into the vessel getting in contact with the liquid metal coolant.… read more here.
Keywords: sodium cooled; cover gas; cooled fast; gas ... See more keywords