13 results on '"Busby, J. T."'
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2. Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions
3. Effect of Thermal Aging on Coarsening Kinetics of γ′ in Alloy 617
4. Radiation damage concerns for extended light water reactor service
5. Cladding and duct materials for advanced nuclear recycle reactors
6. Origin and Influence of Pre-Existing Segregation on Radiation-Induced Segregation in Austenitic Stainless Steels
7. Post-Irradiation Annealing of Dislocation Microstructure and Radiation-Induced Segregation in Proton-Irradiated Stainless Steels
8. Microchemistry of Proton-Irradiated Austenitic Alloys under Conditions Relevant to LWR Core Components
9. Influence of Initial Grain Boundary Composition on the Evolution of Radiation-Induced Segregation Profiles
10. Modeling the Effect of Irradiation and Post-Irradiation Annealing on Grain Boundary Composition in Austenitic Fe-Cr-Ni Alloys
11. High Spatial Resolution X-Ray Microanalysis of Radiation-Induced Segregation in Proton-Irradiated Stainless Steels
12. The Mechanism of Zr and Hf in Reducing Radiation-Induced Segregation in 316 Stainless Steel.
13. Space Fission Reactor Structural Materials: Choices Past, Present, and Future.
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