Simulation of loss-of-flow transients in research reactors
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Cited by (43)
Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor
2022, Annals of Nuclear EnergyExtension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies
2021, Nuclear Engineering and DesignFAST (floating absorber for safety at transient) for the improved safety of sodium-cooled burner fast reactors
2021, Nuclear Engineering and TechnologyTransient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1
2020, Annals of Nuclear EnergyCitation Excerpt :The IAEA benchmark establishes LOFA and RIA as transient scenarios. For the benchmark simulations, a hot subchannel was considered to analyze the transients while an average subchannel represents the general core behavior (remainder) for the feedback calculations (Housiadas, 2000; Lu et al., 2009). Table 3 shows the simulation results from fast loss of flow (FLOFA) and slow loss of flow (SLOFA) transients.
Study of the possibility of switching from natural to forced convection cooling during research reactor operation
2020, Progress in Nuclear Energy
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