103 results on '"Kim, Eung-Seon"'
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2. Fatigue life curves of alloy 617 in the temperature range of 800–950 °C
3. High-temperature tensile behavior of diffusion-welded hastelloy X
4. Enhanced joint integrity of diffusion-welded Alloy 617 by controlling the micro-chemistry near the surface
5. Creep and creep crack growth behaviors for base, weld, and heat affected zone in a grade 91 weldment
6. High-temperature mechanical behaviors of diffusion-welded Alloy 617
7. Diffusion Coefficients Calculations of 110mag in Zrc at Very High Temperature Using Machine-Learning Interatomic Potential
8. Tension and creep rupture behaviors of Alloy 617 thermally aged for a year at 900 °C
9. Application of compressible Reynolds-averaged governing equations to turbulent mixed convection in supercritical fluids in heated vertical tubes
10. Diffusion Welding of Surface Treated Alloy 800H
11. Evaluation of the low cycle fatigue failure properties for GTAW weldments of Alloy 617 at 950 °C
12. Creep and creep-rupture of Alloy 617
13. Numerical simulation of upward flowing supercritical fluids using buoyancy-influence-reflected turbulence model
14. Assessment of low-Reynolds number k-ε turbulence models against highly buoyant flows
15. Influence of Dynamic Strain Aging on Tensile Deformation Behavior of Alloy 617
16. Improvement of long-term creep life extrapolation using a new master curve for Grade 91 steel
17. Numerical simulation of supercritical pressure fluids with property-dependent turbulent Prandtl number and variable damping function
18. Estimation of graphite dust production in ITER TBM using finite element method
19. Fatigue life curves of alloy 617 in the temperature range of 800–950 °C
20. Characterization of the Q* parameter for evaluating creep crack growth rate for type 316LN stainless steel
21. A review of low-cycle fatigue of Alloy 617 for use in VHTR components: Experimental outlook
22. Oxidation behavior of IG and NBG nuclear graphites
23. Optimum coating layer thicknesses of a TRISO having an 800-μm UO2 kernel under normal operation conditions of a 10-MWth block-type HTGR
24. Creep Behavior of Diffusion-Welded Alloy 617
25. UO2 Spheres Produce by External Gelation Process
26. Low-Cycle Fatigue Behavior of Alloy 800H at a High Temperature of 850°C
27. Low Cycle Fatigue and Life Prediction of Alloy 800H Weldment at 750℃
28. Uniform Heated Scaled-Down Standard Fuel Block Test to Validate Core Thermofluid Analysis Code for Prismatic Gas-Cooled Reactor
29. Microstructural effects on the fretting wear of Inconel 690 steam generator tube
30. Effect of spheroidization on the near-threshold fatigue crack growth in ferrite-pearlite steel
31. Uniaxial Low-Cycle Fatigue Study of Alloy 800H Weldments at 700 °C
32. Assessment of Creep Crack Growth Rates for Grade 91 Weld Joint at 550°C
33. Low Cycle Fatigue Behavior of Alloy 800H Base Metal and Weldments at 700°C
34. Effects of Surface Roughness on the Thermal Emissivity of IG-11 Graphite for Nuclear Reactor
35. Nuclear Graphites (II) : Mechanical Properties
36. Influence of Dynamic Strain Aging on Tensile Deformation Behavior Of Alloy 617
37. High-Temperature Structural Analysis of a Lab-Scale Alloy 800HT PCHE
38. Enhancing the oxidation resistance of graphite by applying an SiC coat with crack healing at an elevated temperature
39. Design Characteristics Analysis for Very High Temperature Reactor Components
40. Macro and Microscopic Investigation on Fracture Specimen of Alloy 617 Base Metal and Weldment in Low Cycle Fatigue Regime
41. Nuclear Hydrogen Production Technology Development Using Very High Temperature Reactor
42. Correlation Between Transient Regime and Steady-State Regime on Creep Crack Growth Behavior of Grade 91 Steel
43. Feasibility study of fusion breeding blanket concept employing graphite reflector
44. Characterization of 3 MeV H + irradiation induced defects in nuclear grade graphite
45. Estimation of Graphite Dust Production in a Pebble-Bed Type Nuclear Reflector
46. Effects of Surface Roughness on the Thermal Emissivity of IG-11 Graphite for Nuclear Reactor
47. Thermal Emissivity of Nuclear Graphite as a Function of its Oxidation Degree (3): Structural Study using Scanning Electron Microscope and X-Ray Diffraction
48. Characterization of 3 MeV H+ irradiation induced defects in nuclear grade graphite
49. Nuclear Graphites (II) : Mechanical Properties
50. Thermal Emissivity of a Nuclear Graphite as a Function of Its Oxidation Degree (2) - Effect of Surface Structural Changes -
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