327 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. Silicon Carbide as Plasma Facing or Blanket Material
10. Deuterium retention of low activation ferritic steel and boronized wall in JFT-2M
11. Hydrogen retention and depth profile in divertor tiles of Jt-60 exposed to hydrogen discharges
12. Material probe analysis of boronized wall in LHD
13. Progress of plasma surface interaction study on low activation materials
14. Deuterium retention and desorption behavior of boron–titanium as first wall material of fusion experimental device
15. Effect of heat treatment on helium trapping in vanadium alloy at high ion implantation fluence
16. Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges
17. Energy and fluence dependences of helium retention in stainless steel
18. Hydrogen retention in divertor tiles used in JT-60 for hydrogen discharge period
19. Retention characteristics of hydrogen isotopes in JT-60U
20. Hydrogen retention of carbon dust produced in JT-60
21. Hydrogen isotope distributions and retentions in the inner divertor tile of JT-60U
22. Helium gas permeability of SiC/SiC composite used for in-vessel components of nuclear fusion reactor
23. Retention and desorption of hydrogen and helium in stainless steel wall by glow discharge
24. Morphological change of polycrystalline copper after ion irradiation followed by annealing
25. Hydrogen retention of carbon dust prepared by arc discharge and electron beam irradiation
26. Surface smoothness of polycrystalline copper after ion irradiation
27. Enhancement of reactive species density in nitrogen plasma by mixture of helium and nitridation experiment for silicon
28. Deuterium retention in V–4Cr–4Ti alloy after deuterium ion irradiation
29. Deuterium retention in carbon dust and carbon–tungsten mixed dust prepared by deuterium arc discharge
30. Depth profile and retention of hydrogen isotopes in graphite tiles used in the W-shaped divertor of JT-60U
31. Major results of the cooperative program between JAERI and universities using plasma facing materials in JT-60U
32. Correlation between hydrogen isotope profiles and surface structure of divertor tiles in JT-60U
33. Investigation of compatibility of low activation ferritic steel with high performance plasma by full covering of inside vacuum vessel wall on JFT-2M
34. Plasma material interaction studies on low activation materials used for plasma facing or blanket component
35. Impurity release and deuterium retention properties of a ferritic steel wall in JFT-2M
36. Material probe study for plasma facing wall of LHD
37. Serum pepsinogen can predict response to H2-receptor antagonist in patients with functional dyspepsia
38. Helium retention of B4C or SiC converted graphite
39. Evaluation of hydrogen sorption and desorption for Ti-6A1-4V alloy as a vacuum vessel material
40. Hydrogen isotope behavior in in-vessel components used for DD plasma operation of JT-60U by SIMS and XPS technique
41. Suppression of hydrogen absorption to V–4Cr–4Ti alloy by TiO 2/TiC coating
42. Analysis for surface probes of third experimental campaign in the large helical device
43. Blister formation and erosion due to blister fracture of SiC or Si
44. Tritium inventory of carbon dust in ITER
45. Gas permeability of SiC/SiC composites as fusion reactor material
46. Effect of mixing of hydrogen into nitrogen plasma
47. Bubble formation on silicon by helium ion bombardment
48. Measurement on helium atom temperature in the vicinity of substrate in low temperature plasma
49. Deuterium retention of V–4Cr–4Ti alloy exposed to the JFT-2M tokamak environment
50. Performance of V–4Cr–4Ti alloy exposed to the JFT-2M tokamak environment
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