35 results on '"Busby, J. T."'
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2. Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
3. Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels
4. Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
5. Thermal Aging Phenomena in Cast Duplex Stainless Steels
6. Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions
7. Effect of Thermal Aging on Coarsening Kinetics of γ′ in Alloy 617
8. Radiation damage concerns for extended light water reactor service
9. Cladding and duct materials for advanced nuclear recycle reactors
10. Origin and Influence of Pre-Existing Segregation on Radiation-Induced Segregation in Austenitic Stainless Steels
11. Post-Irradiation Annealing of Dislocation Microstructure and Radiation-Induced Segregation in Proton-Irradiated Stainless Steels
12. Microchemistry of Proton-Irradiated Austenitic Alloys under Conditions Relevant to LWR Core Components
13. Influence of Initial Grain Boundary Composition on the Evolution of Radiation-Induced Segregation Profiles
14. Modeling the Effect of Irradiation and Post-Irradiation Annealing on Grain Boundary Composition in Austenitic Fe-Cr-Ni Alloys
15. Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
16. High Spatial Resolution X-Ray Microanalysis of Radiation-Induced Segregation in Proton-Irradiated Stainless Steels
17. Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
18. Grain boundary engineering for structure materials of nuclear reactors
19. Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions
20. Thermal Aging Phenomena in Cast Duplex Stainless Steels
21. Corrosion Behavior of Model Zirconium Alloys in Deaerated Supercritical Water at 500°C
22. Space fission reactor structural materials: Choices past, present, and future
23. Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking
24. Effect of proton and Ne irradiation on the microstructure of Zircaloy 4
25. Post-irradiation annealing of small defect clusters
26. Dose Dependence of Radiation Induced Segregation in Proton Irradiated Austen1tic Alloys
27. The Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316 Stainless Steel.
28. Emulation of neutron irradiation effects with protons: validation of principle
29. On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Ni alloys
30. Correlation between swelling and radiation-induced segregation in iron-chromium-nickel alloys
31. Microstructural effect on neutron irradiation response of alloy 800H
32. LAMDA: A facility for advanced characterization of irradiated materials at Oak Ridge national laboratory
33. Refractory alloys for nuclear applications
34. Grain boundary engineering for structure materials of nuclear reactor
35. Computational thermodynamics for interpreting oxidation of structural materials in supercritical water
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