Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor - Concepedia

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Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor

DOI Full Paper Access

19

Citations

4

References

2016

Year

Kevin Schillo, Akansha Kumar, Kurt Harris, Yayu M. Hew, Steven Howe

Annals of Nuclear Energy

EngineeringNuclear EngineeringNuclear FuelThermal HydraulicsNuclear Fuel EnrichmentThermal Hydraulics AnalysisNuclear PowerNuclear Reactors

References

	Year	Citations

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