Concepedia

Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing

Kenichi Ohmae, Akikazu Morino, Noboru Nakao, Seizo Hirao

Nuclear Engineering and Design · 1972 · 17 citations · 2 references

Concepts

EngineeringMechanical EngineeringNuclear EngineeringHeat TransferMechanical Behavior Of MaterialsThermal AnalysisDuctilityElastic DeformationHeat Transfer In ReactorsNuclear Fuel MaterialsReactor DesignThermal-hydraulic Safety AnalysisBuckling TheoryDeformation AnalysisFuel Channel Blockage AnalysisFuel Rod BowingFuel SwellingStructural Deformation AnalysisSwelling Of Nuclear Fuel

References

2

NUCLEAR REACTOR CORE ANALYSIS CODE: CITATION.

T.B. Fowler, D.R. Vondy · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1970 · 285 citations

Engineering, Nuclear Engineering, Physics +12

COOLANT INTERCHANNEL MIXING IN REACTOR FUEL ROD BUNDLES: SINGLE-PHASE COOLANTS.

J. T. Rogers, N.E. Todreas · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1969 · 33 citations

Engineering, Chemical Engineering, Nuclear Engineering +9