302 results on '"Qiu, S.Z."'
Search Results
2. Program development for mass flowrate distribution optimization in the nuclear power plant
3. Numerical investigation on heat transfer and pressure drop characteristics of moisture separator reheater with porous media method
4. Experimental study on fuel rod melting based on alternative materials
5. An investigation of characteristics of flow and heat transfer in the two-layer molten pool under swing motion condition
6. Analysis of CHF characteristics with fuel rods in the natural circulation system under motion conditions
7. Analysis of the natural circulation system characteristics with fuel rods under motion conditions
8. Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident
9. Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head
10. Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor
11. Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic
12. Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation
13. A study on the dynamic characteristics of the secondary loop in nuclear power plant
14. A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection
15. Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels
16. Experimental research on the influence of rolling motions on the convection behaviors inside two-layer corium pools
17. Experimental study on leak flow rate characteristics of high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under high back pressure conditions
18. Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition
19. A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics
20. Experimental study of raining effect on the inner surface of containment roof
21. A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding
22. Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions
23. Experimental study on the flow and thermal characteristics of two-phase leakage through micro crack
24. Theoretical prediction of single bubble motion in vertically upward two-phase flow across inclined tube bundles
25. Effect of stratified interface instability on thermal focusing effect in two-layer corium pool
26. Effects of nitrogen and carbon monoxide on the detonation of hydrogen-air gaseous mixtures
27. Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle
28. A new method on fluid-to-fluid scaling for heat transfer in tubes at supercritical pressures
29. Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition
30. Flow pattern effect on two-phase pressure drops in vertical upward flow across a horizontal tube bundle
31. Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors
32. Development of a multi-compartment containment code for advanced PWR plant
33. Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms
34. Models development of liquid drops entrainment at a T-junction with a large vertical up branch
35. A 3-D simulation tool for hydrogen detonation during severe accident and its application
36. Experiment research on thermal mixing in horizontal T-junction: In-pipe temperature and flow characteristic research
37. Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle
38. The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR
39. Pressure drop characteristics of vertically upward flow in inclined rod bundles
40. Development of a thermal-hydraulic subchannel analysis code for motion conditions
41. Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core
42. ECC condensation research in T-junction
43. Experimental simulation of liquid entrainment in ADS-4 depressurization line in AP1000
44. Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model
45. Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor
46. Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition
47. Pressure drop characteristics of two-phase flow in a vertical rod bundle with support plates
48. The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head
49. Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers – Results of COPRA experiments
50. Development and verification of molten corium–concrete interaction code
Catalog
Books, media, physical & digital resources
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.