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1. Recent progress of JT-60SA project toward plasma operation

2. Reply to Comment on ‘Deuterium supersaturated surface layer in tungsten: ion energy dependence’

3. Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device

4. Evaluation of heat removal property in W/Cu/RAFM steel joint by using electron beam facility

5. Deuterium supersaturated surface layer in tungsten: ion energy dependence

6. Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

7. Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

8. Enhanced D retention in RAFM steel caused by D bubbles formed inside Cr-rich surface layer

9. Investigation on tritium retention and surface properties on the first wall in the large helical Device

10. Influence of thermal shocks on the He induced surface morphology on tungsten

11. Demonstration of suppression of dust generation and partial reduction of the hydrogen retention by tungsten coated graphite divertor tiles in LHD

12. Tritium retention characteristics in dust particles in JET with ITER-like wall

13. Investigation of the distribution of remaining tritium in divertor in LHD

14. Global distribution of tritium in JET with the ITER-like wall

15. Impact of seeded plasma impurities on D retention in RAFM steels

16. Thermal stability and evolution of microstructures induced by He irradiation in W–TiC alloys

17. The role of the graphite divertor tiles in helium retention on the LHD wall

18. Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

19. Wide-range evaluation of the deposition layer thickness distribution on the first wall by reflection coefficient measurements

20. Initial growth phase of W-fuzz formation in ultra-long pulse helium discharge in LHD

21. Damage and deuterium retention of re-solidified tungsten following vertical displacement event-like heat load

22. Application of optical reflectivity measurements to diagnostics for plasma facing materials

23. Effect of impurity deposition layer formation on D retention in LHD plasma exposed W

24. Global scaling of the heat transport in fusion plasmas

25. DAMAGING OF PURE TUNGSTEN WITH DIFFERENT MICROSTRUCTURE UNDER SEQUENTIAL QSPA AND LHD PLASMA LOADS

26. Enhanced D retention in RAFM steel caused by D bubbles formed inside Cr-rich surface layer

27. Deuterium and helium retention in W with and without He-induced W ‘fuzz’ exposed to pulsed high-temperature deuterium plasma

28. Thermal stability of microstructures and mechanical properties in a Fe-based Fe-Cr-Mn-Cu-Mo multi-component alloy

29. Tritium retention characteristic in dust particles in JET with ITER-like wall

30. Influence of Hydrogen at the Interface on Tensile Properties of Equiatomic FeCrNiMnCo High-Entropy Alloy

31. An overview of tritium retention in dust particles from the JET-ILW divertor

32. Surface morphology of F82H steel exposed to low-energy D plasma at elevated temperatures

33. Heat loading behavior and thermomechanical analyses on plasma spray tungsten coated reduced-activation ferritic/martensitic steel

34. Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation

35. Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

36. Material migration in W and Mo during bubble growth and fuzz formation

37. Advanced multi-step brazing for fabrication of a divertor heat removal component

39. Surface modification and sputtering erosion of reduced activation ferritic martensitic steel F82H exposed to low-energy, high flux deuterium plasma

40. Modifications of WNOx films by keV D and H ions

41. Material mixing during fuzz formation in W and Mo

43. Plasma wall interaction in long-pulse helium discharge in LHD – Microscopic modification of the wall surface and its impact on particle balance and impurity generation

44. Effect of the RF wall conditioning on the high performance plasmas in the Large Helical Device

45. Global helium particle balance in LHD

46. Preparation of erosion and deposition investigations on plasma facing components in Wendelstein 7-X

47. Overview of the JET results in support to ITER

48. Analysis of radiation environment at divertor in helical reactor FFHR-d1

49. Comparison of hydrogen isotope retention for tungsten probes in LHD vacuum vessel during the experimental campaigns in 2011 and 2012

50. Observation of increased nanostructure cone growth on Cr due to grazing-incidence Ta seed atom deposition in a He plasma

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