115 results on '"Hirohata, Y."'
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2. Deuterium retention and desorption behavior in oxidized ferritic steel
3. Hydrogen isotopes retention in JT-60U
4. Plasma wall interaction study in the large helical device
5. Hydrogen isotope behavior in the first wall of JT-60U after deuterium plasma operation
6. Distribution of hydrogen isotopes retained in the divertor tiles used in JT-60U
7. Retention and desorption behavior of helium in oxidized V–4Cr–4Ti alloy
8. Helium gas permeability of SiC/SiC composite after heat cycles
9. Deuterium retention of low activation ferritic steel and boronized wall in JFT-2M
10. Hydrogen retention and depth profile in divertor tiles of Jt-60 exposed to hydrogen discharges
11. Material probe analysis of boronized wall in LHD
12. Progress of plasma surface interaction study on low activation materials
13. Deuterium retention and desorption behavior of boron–titanium as first wall material of fusion experimental device
14. Effect of heat treatment on helium trapping in vanadium alloy at high ion implantation fluence
15. Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges
16. Energy and fluence dependences of helium retention in stainless steel
17. Hydrogen retention in divertor tiles used in JT-60 for hydrogen discharge period
18. Retention characteristics of hydrogen isotopes in JT-60U
19. Hydrogen retention of carbon dust produced in JT-60
20. Hydrogen isotope distributions and retentions in the inner divertor tile of JT-60U
21. Helium gas permeability of SiC/SiC composite used for in-vessel components of nuclear fusion reactor
22. Retention and desorption of hydrogen and helium in stainless steel wall by glow discharge
23. Morphological change of polycrystalline copper after ion irradiation followed by annealing
24. Hydrogen retention of carbon dust prepared by arc discharge and electron beam irradiation
25. Deuterium retention in V–4Cr–4Ti alloy after deuterium ion irradiation
26. Deuterium retention in carbon dust and carbon–tungsten mixed dust prepared by deuterium arc discharge
27. Depth profile and retention of hydrogen isotopes in graphite tiles used in the W-shaped divertor of JT-60U
28. Major results of the cooperative program between JAERI and universities using plasma facing materials in JT-60U
29. Correlation between hydrogen isotope profiles and surface structure of divertor tiles in JT-60U
30. Investigation of compatibility of low activation ferritic steel with high performance plasma by full covering of inside vacuum vessel wall on JFT-2M
31. Plasma material interaction studies on low activation materials used for plasma facing or blanket component
32. Impurity release and deuterium retention properties of a ferritic steel wall in JFT-2M
33. Material probe study for plasma facing wall of LHD
34. Hydrogen isotope behavior in in-vessel components used for DD plasma operation of JT-60U by SIMS and XPS technique
35. Suppression of hydrogen absorption to V–4Cr–4Ti alloy by TiO 2/TiC coating
36. Analysis for surface probes of third experimental campaign in the large helical device
37. Blister formation and erosion due to blister fracture of SiC or Si
38. Tritium inventory of carbon dust in ITER
39. Gas permeability of SiC/SiC composites as fusion reactor material
40. Effect of mixing of hydrogen into nitrogen plasma
41. Bubble formation on silicon by helium ion bombardment
42. Measurement on helium atom temperature in the vicinity of substrate in low temperature plasma
43. Deuterium retention of V–4Cr–4Ti alloy exposed to the JFT-2M tokamak environment
44. Performance of V–4Cr–4Ti alloy exposed to the JFT-2M tokamak environment
45. Hydrogen retention and erosion of carbon–tungsten mixed material
46. Dependence of surface oxidation on hydrogen absorption and desorption behaviors of Ti–6Al–4V alloy
47. Helium retention of plasma facing materials
48. Hydrogen absorption/desorption behavior with oxygen-contaminated boron film
49. Deuterium retention of DIII-D DiMES sample
50. Deuterium retention and desorption behavior in oxidized ferritic steel
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