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120 results on '"ZIRCALOY-2"'

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1. Heat of transport for hydrogen and hydrides in Zircaloy.

2. 基于机器学习的锆合金在 360 °C/18.6 MPa 溶氧水中腐蚀预测方法研究.

3. The Corrosion and Mechanical Behavior of Zirconium Alloy for Alkali Fusion Process at High Temperature.

4. Assessing the fracture toughness of Zircaloy-4 fuel rod cladding tubes: impact of delayed hydride cracking.

5. Study of PEO on zirconium alloy for coating thickness diagnostics.

6. Effect of Boron Content in LiOH Solutions on the Corrosion Behavior of Zr-Sn-Nb Alloy.

7. Vacuum sealing-assisted processing of titanium–zirconium alloys: synthesis, microstructure, hardness, friction, wear, and corrosion studies for biomedical application.

8. Properties of silicon dioxide coatings obtained by nano physical vapor deposition (PVD) method on the titanium 13‐niobium 13‐zirconium alloy.

9. Understanding the high-temperature corrosion behavior of zirconium alloy as cladding tubes: a review.

10. Fuzzy based modeling and optimization of EDMed response of Zircaloy-2.

11. Analysis of the advanced PWR cell MOX fuel using SiC, Zr, FeCrAl, and SS-310 as cladding materials.

12. Analysis of morphology and corrosion resistance coating formed on Zr-4 substrate by anodizing.

13. Dislocation Hardening in a New Manufacturing Route of Ferritic Oxide Dispersion-Strengthened Fe-14Cr Cladding Tube.

14. Structure and Oxidation Behavior of a Chromium Coating on Zr Alloy Cladding Tubes Deposited by High-Speed Laser Cladding.

15. Jetting in Cylindrical Cumulation.

16. Improved oxidation resistance of Cr-Si coated Zircaloy with an in-situ formed Zr2Si diffusion barrier.

17. How can machine learning be used for accurate representations and predictions of fracture nucleation in zirconium alloys with hydride populations?

18. Mechanical properties behaviour using PADBT for the nuclear reactor cladding (Aluminium alloy 6061) after irradiation.

19. Feeder Pipe Oxidation in the Presence of Steam During a Nuclear Reactor Accident.

20. Investigation of AL/CU Bimetallic Tube Cladding Process by Severe Plastic Deformation.

21. Simulation study on the effect of ODS cladding material on the criticality of nuclear reactors using MCNP5.

22. Hydrogen Solubility in Zirconium Alloys E110opt and E635.

23. Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing.

24. Machining of Zircaloy-2 using progressive tool design in EDM.

25. An Orthogonal Experimental Study on the Preparation of Cr Coatings on Long-Size Zr Alloy Tubes by Arc Ion Plating.

26. Free Intermetallic Cladding Interface between Aluminum and Steel through Friction Stir Processing.

27. Plastic flow instability at the parabolic stage in technical Zirconium alloys.

28. Effect of Impact Velocity and Angle on Impact Wear Behavior of Zr-4 Alloy Cladding Tube.

29. Effect of Ultrasonic Vibration Frequency on Ni-Based Alloy Cladding Layer.

30. Surface Properties of Medium-Entropy Alloy Coatings Prepared through a Combined Process of Laser Cladding and Ultrasonic Burnishing.

31. Metallurgical evolution and interfacial interactions between 304L stainless steel and Zy-4 alloy dissimilar junction during isothermal holding at high temperature.

32. E110-Type Zirconium Alloys – Dilatometric Determination of Solidus and Liquidus Temperatures.

33. Influence of Deformation on the Hydrogen Saturation of Zr–1%Nb Alloy After Oxidation and Nitriding.

34. Effect of TiC on Microstructure and Properties of Wear-Resistant Mo 2 FeB 2 Claddings.

35. Jules Horowitz Reactor Irradiation Devices: Inspection Methods proposal.

36. Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa.

37. High-Temperature Corrosion of Ni-Cr-Mo Cladding Layers with Different Si Contents in NaCl-KCl-Na 2 SO 4 -K 2 SO 4 Mixed Salt Medium.

38. Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C.

39. Novel Dopant Tailored Fibers Using Vapor Phase Chelate Delivery Technique.

40. An evaluation of the geotechnical characteristics of Gahirat marble using empirical methods: A case study from the Chitral area, Khyber Pakhtunkhwa, North Pakistan.

41. Factors Influencing Reorientation of Hydrides in Unirradiated Cladding Tubes from E110 Alloy under Conditions of Long-Term Dry Storage of SNF.

42. High-resolution transmission electron microscopy study of body-centered tetragonal Zr2Fe nanoparticle phase in Zircaloy-4 alloy and its typical crystalline defect structures.

43. Close-in blast resistance of large-scale auxetic re-entrant honeycomb sandwich panels.

44. Machining and optimization of Zircaloy-2 using different tool electrodes.

45. Modeling of the microstructural behavior of hydrided zirconium alloys.

46. An evaluation of the geotechnical characteristics of Gahirat marble using empirical methods: A case study from the Chitral area, Khyber Pakhtunkhwa, North Pakistan.

47. Comprehensive Analysis of Nanostructure of Oxide Dispersion Strengthened Steels as Prospective Materials for Nuclear Reactors.

48. Denuded zones in zirconium pressure vessels: oxygen's role examined via multi-scale diffusion model.

49. Raman study of oxide layers on zirconium alloys using 18O tracers.

50. Plastic instability of mechanical bulging process for Zircaloy-4 cladding tube based on localized necking criterion.

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