Concepedia

Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code

Yousef Alzaben, Víctor Hugo Sánchez-Espinoza, Robert Stieglitz

Annals of Nuclear Energy · 2019 · 19 citations · 4 references

Concepts

EngineeringNuclear EngineeringPhysicsNuclear PhysicsNuclear Safety AnalysisReactor PhysicsHeat Transfer In ReactorsNeutron AbsorptionNeutron Transport TheoryReactor DynamicsReactor KineticsThermal-hydraulic Safety AnalysisControl Rod Ejection AccidentsControl Rod Ejection AnalysisNeutronic-thermal-hydraulic CouplingSmall Modular ReactorsThermal-hydraulic CodesThermal-hydraulic CouplingThermal-hydraulics

References

4

Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT)

Uwe Imke, Víctor Hugo Sánchez-Espinoza · Science and Technology of Nuclear Installations · 2012 · 80 citations · Full text

Engineering, Computational Engineering, Nuclear Engineering +17

Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

Z. Tabadar, Kamal Hadad, Mohammadreza Nematollahi et al. · Annals of Nuclear Energy · 2012 · 38 citations

Engineering, Aerospace Engineering, Computational Mechanics +6

Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors

C.M. Allison, E. Balabanov, Francesco Saverio D'Auria et al. · 2003 · 28 citations

Engineering, Nuclear Engineering, Risk Management +16

Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors

Yousef Alzaben, Víctor Hugo Sánchez-Espinoza, Robert Stieglitz · Annals of Nuclear Energy · 2019 · 22 citations

Engineering, Nuclear Engineering, Physics +17