34 results on '"Deng, Yangbin"'
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2. Grid-to-rod fretting in nuclear power reactors: Driving mechanisms, research methodologies and mitigation measures
3. Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method
4. Investigation on axial relocation of fragmented annular fuel under loss of coolant accident conditions with discrete element method
5. Investigation on radial fuel relocation and its influence on heat split phenomenon of dual-cooled annular fuel element
6. Investigation on fuel cracking induced relocation behavior of dual-cooled annular fuel based on finite element simulation
7. Design and evaluation of a high power density and high energy efficiency fuel element for space nuclear reactors
8. An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code
9. Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials
10. Creep failure of a solution-annealed 15-15Ti steel exposed to stagnant lead-bismuth eutectic at 550 and 600 °C
11. Effect of temperature on liquid metal embrittlement susceptibility of an Fe10Cr4Al ferritic alloy in contact with stagnant lead-bismuth eutectic
12. 3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition
13. Performance evaluation and efficiency enhancement of a space thermionic fuel element for thermal energy conversion and utilization
14. Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels
15. Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors
16. Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and -saturated lead-bismuth eutectic at 350°C
17. A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding
18. Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel
19. Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs
20. Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel
21. Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element
22. Design and assessment of a core-power controller for lithium-cooled space nuclear reactor based on the concept of fuzzy model predictive control
23. Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs
24. Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions
25. Corrigendum to “Liquid metal embrittlement of an Fe10Cr4Al ferritic alloy exposed to oxygen-depleted and -saturated lead-bismuth eutectic at 350 °C” [Corros. Sci. 165 (2020) 108364]
26. Liquid metal embrittlement susceptibility of a high-entropy alloy exposed to oxygen-depleted liquid lead-bismuth eutectic at 250 and 350 °C
27. Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts
28. Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
29. Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response
30. A comparative study on preliminary performance evaluation of ATFs under normal and accident conditions with FRAP-ATF code
31. Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding
32. A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2for ATF cladding
33. Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel
34. Neuroprotective effect of Panax notoginseng plysaccharides against focal cerebral ischemia reperfusion injury in rats
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