50 results on '"Sugiyama, K."'
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2. Erosion study of Fe–W binary mixed layer prepared as model system for RAFM steel
3. Optimization of tungsten castellated structures for the ITER divertor
4. Surface morphology and deuterium retention in tungsten and tungsten–rhenium alloy exposed to low-energy, high flux D plasma
5. Effect of radiation-induced damage on deuterium retention in tungsten, tungsten coatings and Eurofer
6. Deuterium retention in tungsten damaged with W ions to various damage levels
7. Tritium loading study of tungsten pre-exposed to TEXTOR plasmas
8. Study of deuterium retention in/release from ITER-relevant Be-containing mixed material layers implanted at elevated temperatures
9. Deuterium retention in single-crystal tungsten irradiated with 10–500 eV/D+
10. Deuterium retention in Toughened, Fine-Grained Recrystallized Tungsten
11. Oxidation of beryllium and exposure of beryllium oxide to deuterium plasmas in PISCES B
12. Study of thermal hydrogen atom interaction with undamaged and self-damaged tungsten
13. The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas
14. Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR
15. Trapping of hydrogen isotopes in radiation defects formed in tungsten by neutron and ion irradiations
16. Overview on plasma operation with a full tungsten wall in ASDEX Upgrade
17. Characterization of in-vessel hydrogen isotope retention of JT-60U
18. Deuterium thermal desorption from carbon based materials: A comparison of plasma exposure, ion implantation, gas loading, and C–D codeposition
19. Influence of beryllium carbide formation on deuterium retention and release
20. Global transport of light elements boron and carbon in the full-W ASDEX Upgrade
21. Consequences of deuterium retention and release from Be-containing mixed materials for ITER Tritium Inventory Control
22. Exposure of tungsten nano-structure to TEXTOR edge plasma
23. Ion-induced deuterium retention in tungsten coatings on carbon substrate
24. Influence of thermal treatment on beryllium/carbon formation and fuel retention
25. Removal of the deposition on JT-60 tile by nano-sec pulsed-laser irradiation
26. Tritium removal by isotopic exchange
27. Hydrogen retention in ITER relevant mixed material layers
28. Deuterium depth profiling in graphite tiles not exposed to hydrogen discharges before air ventilation of JT-60U
29. Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade
30. Properties of hydrogen desorption from co-deposits on JT-60 graphite tile by pulsed-laser ablation
31. Tritium distribution measurement of JET Mk II SRP divertor tiles
32. Ion beam analysis of H and D retention in the near surface layers of JT-60U plasma facing wall tiles
33. Deuterium depth profiling in JT-60U tiles using the D(3He, p)4He resonant nuclear reaction
34. Post mortem analysis of a JET quartz microbalance system
35. Hydrogen isotope behavior in the first wall of JT-60U after deuterium plasma operation
36. Distribution of hydrogen isotopes retained in the divertor tiles used in JT-60U
37. Tritium distribution measurement of the tile gap of JT-60U
38. Comparison of tritium retention and carbon deposition in JET and JT-60U
39. Tritium distribution on plasma-facing tiles from ASDEX Upgrade
40. Retention characteristics of hydrogen isotopes in JT-60U
41. Tritium profile in plasma-facing components following D–D operation
42. Tritium distribution on the surface of plasma facing carbon tiles used in JET
43. Tritium distribution in JT-60U W-shaped divertor
44. Deuterium absorption in reduced activation ferritic/martensitic steel F82H under exposure to D2O vapor/water at room temperature
45. Deuterium retention in dense and disordered nanostructured tungsten coatings
46. Effects of tungsten surface conditions on carbon deposition
47. Deuterium depth profiling in JT-60U tiles using the D(3He,p)4He resonant nuclear reaction
48. Deuterium depth profiling in JT-60U tiles using the D(3He,p)4He resonant nuclear reaction
49. The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas.
50. Deuterium retention in single-crystal tungsten irradiated with 10–500 eV/D+.
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