Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers - Concepedia

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Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers

170

Citations

15

References

2013

Year

Yeon Sang Jung, Cheon-Bo Shim, Chang Hyun Lim, Han Gyu Joo

Annals of Nuclear Energy

Numerical AnalysisEngineeringThermal HydraulicsThermal/hydraulic SolversNuclear SafetyNeutron SourceTransport PhenomenaPractical Numerical ReactorHeat TransferNeutron TransportNeutron ScatteringNuclear Engineering

References

	Year	Citations

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