278 results on '"Katoh, Y"'
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2. Effects of sample bias on adhesion of magnetron sputtered Cr coatings on SiC
3. Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: Using nickel isotopes to simulate fusion neutron response
4. Advanced synchrotron characterization techniques for fusion materials science
5. Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys
6. Characterization of PVD Cr, CrN, and TiN coatings on SiC
7. Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopy
8. Response of unalloyed tungsten to mixed spectrum neutrons
9. Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor
10. Deformation analysis of SiC-SiC channel box for BWR applications
11. Recent progress in the development of SiC composites for nuclear fusion applications
12. Development of castable nanostructured alloys as a new generation RAFM steels
13. Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod
14. Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature
15. Helium sequestration at nanoparticle-matrix interfaces in helium + heavy ion irradiated nanostructured ferritic alloys
16. Irradiation effects in tungsten-copper laminate composite
17. Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service
18. Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
19. Modeling and testing miniature torsion specimens for SiC joining development studies for fusion
20. Microstructure and mechanical properties of heat-treated and neutron irradiated TRISO-ZrC coatings
21. Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form
22. Current status and recent research achievements in SiC/SiC composites
23. Irradiation creep of nano-powder sintered silicon carbide at low neutron fluences
24. Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions
25. Thermo-mechanical analysis of LWR SiC/SiC composite cladding
26. Stability of the strengthening nanoprecipitates in reduced activation ferritic steels under Fe2+ ion irradiation
27. Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation
28. Transmutation of silicon carbide in fusion nuclear environment
29. Fabrication and characterization of fully ceramic microencapsulated fuels
30. Silicon carbide composites as fusion power reactor structural materials
31. Joining of SiC-based materials for nuclear energy applications
32. Stability of 3-D carbon fiber composite to high neutron fluence
33. Damage production and accumulation in SiC structures in inertial and magnetic fusion systems
34. DC electrical conductivity of silicon carbide ceramics and composites for flow channel insert applications
35. Recent advances and issues in development of silicon carbide composites for fusion applications
36. Cavity swelling and dislocation evolution in SiC at very high temperatures
37. The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites
38. Microstructural defects in SiC neutron irradiated at very high temperatures
39. Swelling of nuclear graphite and high quality carbon fiber composite under very high irradiation temperature
40. Shear properties at the PyC/SiC interface of a TRISO-coating
41. ITER-Test blanket module functional materials
42. Effect of neutron irradiation on tensile properties of unidirectional silicon carbide composites
43. Irradiation creep of high purity CVD silicon carbide as estimated by the bend stress relaxation method
44. Mechanical properties of advanced SiC/SiC composites after neutron irradiation
45. Swelling of SiC at intermediate and high irradiation temperatures
46. The effects of neutron irradiation on shear properties of monolayered PyC and multilayered PyC/SiC interfaces of SiC/SiC composites
47. Current status and critical issues for development of SiC composites for fusion applications
48. Miniaturized fracture stress tests for thin-walled tubular SiC specimens
49. Microstructural development in cubic silicon carbide during irradiation at elevated temperatures
50. Determining the shear properties of the PyC/SiC interface for a model TRISO fuel
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