171 results on '"Jitsukawa, S."'
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2. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket
3. Heat treatment effect on fracture toughness of F82H irradiated in HFIR
4. Micro-structure and micro-hardness of ODS steels after ion irradiation
5. Recent progress in blanket materials development in the Broader Approach activities
6. Density functional calculations for small iron clusters with substitutional phosphorus
7. High energy heavy ion induced structural disorder in Li 2TiO 3
8. Mechanical properties of SiC/SiC composite with magnesium–silicon oxide interphase
9. Effect of displacement damage up to 50 dpa on microstructural development in SiC/SiC composites
10. Fracture toughness characterization of JLF-1 steel after irradiation in HFIR to 5 dpa
11. Effect of temperature change on the irradiation hardening of the structural alloys for ITER blanket and ITER TBM irradiated to 1.5 dpa in JMTR
12. Mechanical properties and microstructures in F82H steel irradiated under alternating temperature
13. Effects of heat treatment and irradiation on mechanical properties in F82H steel doped with boron and nitrogen
14. Status of reduced activation ferritic/martensitic steel development
15. Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effects studies
16. Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study
17. Radiation hardening and -embrittlement due to He production in F82H steel irradiated at 250 °C in JMTR
18. Synergistic effects of implanted helium and hydrogen and the effect of irradiation temperature on the microstructure of SiC/SiC composites
19. Post irradiation plastic properties of F82H derived from the instrumented tensile tests
20. Effects of heat treatment process for blanket fabrication on mechanical properties of F82H
21. Microstructure property analysis of HFIR-irradiated reduced-activation ferritic/martensitic steels
22. Reduced activation martensitic steels as a structural material for ITER test blanket
23. Recent results of the reduced activation ferritic/martensitic steel development
24. Synergistic effect of displacement damage and helium atoms on radiation hardening in F82H at TIARA facility
25. Waste management for JAERI fusion reactors
26. Fabrication of advanced SiC fiber/F-CVI SiC matrix composites with SiC/C multi-layer interphase
27. Preparation of silicon-based oxide layer on high-crystalline SiC fiber as an interphase in SiC/SiC composites
28. Microstructural study of irradiated isotopically tailored F82H steel
29. Irradiation-assisted SCC susceptibility of HIPed 316LN-IG stainless steel irradiated at 473 K to 1 dpa
30. Evaluation of hardening behaviour of ion irradiated reduced activation ferritic/martensitic steels by an ultra-micro-indentation technique
31. Phase stability and mechanical properties of irradiated Ti–Al–V intermetallic compound
32. Swelling behavior of TIG-welded F82H IEA heat
33. Ferritic/martensitic steels – overview of recent results
34. Microstructure in vanadium irradiated by simultaneous multi-ion beam of hydrogen, helium and nickel ions
35. Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H
36. Microstructural analysis of mechanically tested reduced-activation ferritic/martensitic steels
37. Ab initio study on isotope exchange reactions of H 2 with surface hydroxyl groups in lithium silicates
38. Optimizing the fabrication process for superior mechanical properties in the FCVI SiC matrix/stoichiometric SiC fiber composite system
39. Effect of simultaneous ion irradiation on microstructural change of SiC/SiC composites at high temperature
40. Highly thermal conductive, sintered SiC fiber-reinforced 3D-SiC/SiC composites: experiments and finite-element analysis of the thermal diffusivity/conductivity
41. Characterization of 316L(N)-IG SS joint produced by hot isostatic pressing technique
42. Ab initio study on the mechanism of hydrogen release from the silicate surface in the presence of water molecule
43. Response of reduced activation ferritic steels to high-fluence ion-irradiation
44. Progress and critical issues of reduced activation ferritic/martensitic steel development
45. Interactions between fusion materials R&D and other technologies
46. Deformation mechanisms in 316 stainless steel irradiated at 60°C and 330°C
47. Development of a small specimen test machine to evaluate irradiation embrittlement of fusion reactor materials
48. Properties of precipitation hardened steel irradiated at 323 K in the Japan materials testing reactor
49. Fusion materials development program in the broader approach activities
50. Effects of helium on ductile-brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature
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