227 results on '"Katoh, Y"'
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2. Characterization and qualification of neutron radiation effects – Summary of Japan-USA Joint Projects for 40 years –
3. Effects of sample bias on adhesion of magnetron sputtered Cr coatings on SiC
4. Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation
5. Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: Using nickel isotopes to simulate fusion neutron response
6. Advanced synchrotron characterization techniques for fusion materials science
7. Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys
8. Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs
9. Characterization of PVD Cr, CrN, and TiN coatings on SiC
10. Elastic moduli reduction in SiC-SiC tubular specimen after high heat flux neutron irradiation measured by resonant ultrasound spectroscopy
11. Response of unalloyed tungsten to mixed spectrum neutrons
12. Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor
13. Deformation analysis of SiC-SiC channel box for BWR applications
14. Recent progress in the development of SiC composites for nuclear fusion applications
15. Development of castable nanostructured alloys as a new generation RAFM steels
16. Materials challenges for the fusion nuclear science facility
17. Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy
18. 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
19. Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature
20. Helium sequestration at nanoparticle-matrix interfaces in helium + heavy ion irradiated nanostructured ferritic alloys
21. Irradiation effects in tungsten-copper laminate composite
22. Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service
23. Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
24. Modeling and testing miniature torsion specimens for SiC joining development studies for fusion
25. Microstructure and mechanical properties of heat-treated and neutron irradiated TRISO-ZrC coatings
26. Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form
27. Current status and recent research achievements in SiC/SiC composites
28. Irradiation creep of nano-powder sintered silicon carbide at low neutron fluences
29. Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions
30. Thermo-mechanical analysis of LWR SiC/SiC composite cladding
31. Stability of the strengthening nanoprecipitates in reduced activation ferritic steels under Fe2+ ion irradiation
32. Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation
33. Transmutation of silicon carbide in fusion nuclear environment
34. Fabrication and characterization of fully ceramic microencapsulated fuels
35. Silicon carbide composites as fusion power reactor structural materials
36. Joining of SiC-based materials for nuclear energy applications
37. Stability of 3-D carbon fiber composite to high neutron fluence
38. Damage production and accumulation in SiC structures in inertial and magnetic fusion systems
39. An overview of the US DCLL ITER-TBM program
40. DC electrical conductivity of silicon carbide ceramics and composites for flow channel insert applications
41. Recent advances and issues in development of silicon carbide composites for fusion applications
42. Cavity swelling and dislocation evolution in SiC at very high temperatures
43. The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites
44. Oxidation behavior of SiC/SiC composites for helium cooled solid breeder blanket
45. Recent research and development for the dual-coolant blanket concept in the US
46. Microstructural defects in SiC neutron irradiated at very high temperatures
47. Swelling of nuclear graphite and high quality carbon fiber composite under very high irradiation temperature
48. Shear properties at the PyC/SiC interface of a TRISO-coating
49. ITER-Test blanket module functional materials
50. Effect of neutron irradiation on tensile properties of unidirectional silicon carbide composites
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