21 results on '"NO, H.C."'
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2. A zero-dimensional dryout heat flux model based on mechanistic interfacial friction models for two-phase flow regimes with channel flow in a packed bed
3. Model development for fragment-size distribution based on upper-limit log-normal distribution
4. A simple model for the quench front propagation in a highly superheated particle bed
5. Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling
6. Modeling heat transfer through corrosion product deposits on fuel rods in pressurized water reactors
7. Modeling film boiling within chimney-structured porous media and heat pipes
8. Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors
9. Experimental Studies of Flooding in Nearly Horizontal Pipes
10. Corrigendum to “Modeling crust fracture and water ingression through crust during top-flooding strategy for corium cooling” [Nucl. Eng. Des. 342 (2019) 219–230]
11. Assessment of RELAP5/MOD3.1 for gravity-driven injection experiment in the core makeup tank of the CARR Passive Reactor (CP-1300)
12. Stepwise integral scaling method and its application to severe accident phenomena
13. Effect of virtual mass on the characteristics and the numerical stability in two-phase flows
14. Mass transfer coefficient model for the analysis of volatile species transport between two phases
15. Modelling for post-dryout heat transfer and droplet sizes at low pressure and low flow conditions
16. Experimental study of the effect of pipe length and pipe-end geometry on flooding
17. Stepwise integral scaling method for severe accident analysis and its application to corium dispersion in direct containment heating
18. A PC-based water level controller for nuclear steam generators
19. Instrument failure detection and estimation methodology for the nuclear power plant
20. A dry-spot model of critical heat flux applicable to both pool boiling and subcooled forced convection boiling
21. An Investigation of the Physical Foundations of Two-Fluid Representation of Sodium Boiling in the Liquid-Metal Fast Breeder Reactor
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