176 results on '"Jo, Daeseong"'
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2. Characteristics of self-propelled Leidenfrost droplets on asymmetrically structured surfaces: Evidence for a self-rotation-induced propulsive mechanism
3. Motion of Leidenfrost self-propelled droplets on ratchet in low- and high-temperature regimes
4. Pressure fluctuation analysis for identifying the CHF approaching condition during subcooled flow boiling through a mini-channel
5. Pressure fluctuations preceding critical heat flux during subcooled flow boiling in a one-side heated mini-channel under rolling motion
6. Effects of super-hydrophilicity and orientation of heater surface on bubble behavior and the critical heat flux in pool boiling
7. Experimental consideration for contact angle and force acting on bubble under nucleate pool boiling
8. Gas accumulation induced by temperature rise and sudden pressure drop in an inverse U-bend
9. Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants
10. Measuring void fraction in vertical air–water bubbly flow using echo intensity and visualization techniques
11. Effects on pool boiling critical heat flux (CHF) with different direction and magnitude of additional accelerations due to rolling
12. Experimental study of critical heat flux mechanism on a vertical heated surface under rolling motion
13. Statistical method for determining the onset of nucleate boiling under forced and natural convections in a rectangular channel
14. Multimode film boiling on a horizontal surface in a vertically oscillating system
15. Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution
16. Validation of RELAP5 MOD3.3 code for Hybrid-SIT against SET and IET experimental data
17. Non-intrusive detection of gas–water interface in circular pipes inclined at various angles
18. Critical heat flux (CHF) in pool boiling under static and rolling conditions
19. Acoustically monitoring defects on rotating turbine blades
20. Bubble dynamic parameters during subcooled flow boiling under uniform and non-uniform transverse heat distribution
21. Observation of dissolved gas separation and accumulation in stationary water
22. Surface orientation effects on bubble behaviors and critical heat flux mechanism in saturated water pool
23. Prediction of the minimum point of the pressure drop in a narrow rectangular channel under a transversely non-uniform heat flux
24. Experimental study of bubble behaviors and CHF on printed circuit board (PCB) in saturated pool water at various inclination angles
25. Flow Instability (FI) for subcooled flow boiling through a narrow rectangular channel under transversely uniform and non-uniform heat flux
26. ONB, OSV, and OFI for subcooled flow boiling through a narrow rectangular channel heated on one-side
27. Experimental studies of condensing vapor bubbles in subcooled pool water using visual and acoustic analysis methods
28. Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channel
29. Effect of transverse power distribution on the ONB location in the subcooled boiling flow
30. Numerical analysis for multi-group neutron-diffusion equation using Radial Point Interpolation Method (RPIM)
31. Effect of oxide layer growth on fuel temperature of mini fuel plates
32. Transient analyses of the Jordanian 5 MW research reactor under LOEP accident
33. The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel
34. Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII
35. Transient behaviors of heavy water reflector system during postulated initiating events (PIEs)
36. Safety assessment of U–Mo fuel mini plates irradiated in HANARO reactor
37. Effects of transverse power distribution on thermal hydraulic analysis
38. Experimental consideration for contact angle and force acting on bubble under nucleate pool boiling
39. Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production
40. Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors
41. Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP
42. Transient thermal hydraulic analysis of the IAEA 10 MW MTR reactor during Loss of Flow Accident to investigate the flow inversion
43. Hydrodynamic model of interfacial area for trickling flow in a packed bed
44. Cooling capacity of plate type research reactors during the natural convective cooling mode
45. Investigation of bubble breakup and coalescence in a packed-bed reactor – Part 1: A comparative study of bubble breakup and coalescence models
46. Investigation of bubble breakup and coalescence in a packed-bed reactor – Part 2: Development of a new bubble breakup and coalescence model
47. Cost–benefit analysis of BeO–UO 2 nuclear fuel
48. Effect of coalescence and breakup on bubble size distributions in a two-dimensional packed bed
49. Bubble mechanisms and characteristics at pore scale in a packed-bed reactor
50. Gas Accumulation at Inverse U-Bend Resulted From Sudden Pressure Drop and Temperature Increase
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