856 results on '"Su, G.H."'
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2. Conceptual design of a mobile nuclear-electric hybrid energy storage system based on the heat pipe-cooled reactor
3. CorTAF-LBE: A full scale subchannel-level thermal-hydraulic characteristics analysis code for LBR core based on OpenFOAM
4. Mechanism of Cordyceps militaris in gouty nephropathy explored using network pharmacology and molecular docking technology
5. Development of modular dynamic code for steam power conversion system in sodium-cooled fast reactor
6. Study on eutectic-oxidation coupling reaction of Cr-Zr system in high temperature steam environment
7. Simulation of nuclear fuel clad high-temperature ballooning under loss-of-coolant accident conditions considering anisotropic creep
8. Isothermal experiments on eutectic and oxidation reactions of Cr-coated Zr alloy cladding in steam at 1350 ℃: Behavior, mechanism and kinetics
9. Experiment study on the flow mechanism of the molten pool relocation using simulant materials at room temperature
10. Thermal and hydraulic characteristics analysis of horizontal lead-bismuth reactor assembly based on sub-channel analysis code
11. Review, numerical validation, and experiment verification for Definite solution Analogy Theory (DSAT) in thermal-hydraulic scaling
12. Numerical study on benchmark analysis of NACIE-UP facility with uniform and non-uniform power distribution
13. Experimental study on flow and heat transfer of High-Pressure helium flow in compact helical tube heat exchanger in HTGR
14. Investigations of sodium droplet spreading and evaporation on surfaces with different wettability based on lattice Boltzmann simulations
15. Numerical investigation on the effect of different factors on the flow-induced vibration of wire-wrapped fuel rod under axial flow
16. Comparison study of two control strategies for the small pressurized water reactor
17. Artificial neural network for geometric design and optimization of three-stage segmented thermoelectric generators
18. Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model
19. Safety analysis code development and validation for lead-cooled fast reactor with helical coiled once-through steam generator
20. Numerical study of anisotropic scattering and solar radiation impact on liquid droplet radiator performance
21. Experimental and numerical research on the debris bed formation in severe accidents of nuclear reactors
22. Thermal-hydraulic analysis of a full-scale lead-bismuth cooled fast reactor core considering inter-wrapper flow
23. Study on flow regime prediction model for water-cooled reactor core based on machine learning algorithms
24. A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor
25. Numerical investigations on the droplet moving in steam with non-condensable gas by lattice Boltzmann method
26. Experimental study on flow and heat transfer of medium-Prandtl-number fluid along a hexagonal helical cruciform seven-rods
27. High-temperature steam oxidation experiment of molten zirconium alloy
28. Model predictive control for automatic operation of space nuclear reactors: Design, simulation, and performance evaluation
29. Two parallel methods for the three-dimensional CFD coupling simulation of shell and tube heat exchangers
30. LBM study on the heat and mass transfer characteristics of the droplet in pressurizer
31. Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR): An integrated nuclear-based energy production and conversion system
32. Exergy analysis of biomass and nuclear hydrogen production system
33. Corrosion effect analysis on thermal-hydraulics of LBE/water spiral tube steam generator under oxygen-controlled environment
34. Analysis of the effect of thermal stratification on the natural circulation decay heat removal of sodium-cooled fast reactor
35. Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere
36. Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions
37. Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics
38. Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmark
39. Multiphase simulation of hyperbaric steam-water jet inside liquid Pb-Bi eutectic environment
40. Multi-scale coupling analysis of the flow blockage accident in the typical LFR
41. Numerical analysis of thermal-hydraulic characteristics of the whole LFR core under blockage conditions
42. Numerical modeling of alkali metal heat pipes
43. The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0
44. Comparative study of two quick-analysis models for frozen startup of high-temperature heat pipes
45. Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling
46. Study on the characteristics of axial fluid excitation on fuel rods with spacer grids
47. Steady-state multi-physics coupling analysis of heat pipe cooled reactor core
48. Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket
49. Multi-objective optimization design of TRISO-based fully ceramic microencapsulated fuel
50. A review of liquid metal high temperature heat pipes: Theoretical model, design, and application
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