65 results on '"Kasada, R."'
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2. Microstructure development in cryogenically rolled oxide dispersion strengthened copper
3. Positron annihilation study on the phase transition of thermally aged Fe-Cr binary alloys at 748K
4. Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel
5. Irradiation Hardening and Microstructural Evolution in Fe-Cu Model Alloys
6. Two-Step Recovery Process of Irradiation Hardening in 1%Ni Doped 9%Cr-2%W Martensitic Steel
7. Recrystallization of cold rolled oxide dispersion strengthened copper during room temperature annealing
8. Micro- and macro- elastic properties of tungsten fiber-reinforced tungsten composites probed by nano-indentation and laser ultrasonics
9. Microstructure development and high tensile properties of He/H2 milled oxide dispersion strengthened copper
10. Brass-texture induced grain structure evolution in room temperature rolled ODS copper
11. Investigation of mechanical properties of stress-relieved and electron-irradiated tungsten after hydrogen charging
12. In-situ fabrication of yttria dispersed copper alloys through MA-HIP process
13. Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application
14. Detection of phase separation of neutron-irradiated Fe–Cr binary alloys using positron annihilation spectroscopy
15. Longitudinal and shear wave velocities in pure tungsten and tungsten fiber-reinforced tungsten composites
16. Chemical State Mapping of Degraded B4C Control Rod Investigated with Soft X-ray Emission Spectrometer in Electron Probe Micro-analysis
17. Effects of tensile stress on Cu clustering in irradiated Fe–Cu alloy
18. Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus
19. Compatibility of Ni and F82H with liquid Pb–Li under rotating flow
20. Evaluation of Ductile-Brittle Transition Behavior of Helium-implanted Reduced Activation 9Cr-2W Martensitic Steel by Small Punch Tests
21. Relation Between Resistivity and Mechanical Properties in Heat Affected Zone of Welded Pressure Vessel Steel
22. Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
23. Effects of Copper Concentration and Neutron Flux on Irradiation Hardening and Microstructure Evolution in Fe-Cu Model Alloys
24. Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel
25. Grain Boundary Phosphorous Segregation and Its Influence on the Ductile Brittle Transition Temperature in Reactor Pressure Vessel Steels
26. Nanoindentation hardness and its extrapolation to bulk-equivalent hardness of F82H steels after single- and dual-ion beam irradiation
27. Effect of nickel content on the neutron irradiation embrittlement of Ni-Mo-Cr steels
28. High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel
29. Anisotropic heat transfer characteristics of composite material enhanced with high thermal conductivity fiber
30. Operation scenario of DT fusion plant without external initial tritium
31. Ion-Irradiation Hardening of Brazed Joints of Tungsten and Oxide Dispersion Strengthened (ODS) Ferritic Steel
32. Recent progress of tungsten R&D for fusion application in Japan
33. Evaluation of fracture behavior of recrystallized and aged high-Cr ODS ferritic steels
34. Small specimen test technology and methodology of IFMIF/EVEDA and the further subjects
35. Anisotropy in tensile and ductile–brittle transition behavior of ODS ferritic steels
36. Influence of alloy composition and temperature on corrosion behavior of ODS ferritic steels
37. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems
38. Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels
39. Positron annihilation lifetime measurements of He-ion-irradiated Fe using pulsed positron beam
40. Effects of stress on radiation hardening and microstructural evolution in A533B steel
41. Corrosion behaviour of 16%Cr–4%Al and 16%Cr ODS ferritic steels under different metallurgical conditions in a supercritical water environment
42. Compatibility of materials for advanced blanket with liquid LiPb
43. Fusion materials development program in the broader approach activities
44. Effects of helium on ductile-brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature
45. Stability of Y–Ti complex oxides in Fe–16Cr–0.1Ti ODS ferritic steel before and after heavy-ion irradiation
46. Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels
47. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules
48. Impact of N-isotope composition control of ferritic steel on classification of radioactive materials from fusion reactor
49. Pre- and post-deformation microstructures of oxide dispersion strengthened ferritic steels
50. Effects of neutron irradiation on the tensile properties of high-Cr oxide dispersion strengthened ferritic steels
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