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5. Hydrogen removal by electron cyclotron wall conditioning with neon gas and its impact of tokamak plasma start-up on the QUEST spherical tokamak

12. Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration

13. Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-LIKE WALL

20. A reduced-turbulence regime in the Large Helical Device upon injection of low-Z materials powders

21. Plasma Wall Interaction of New Type of Divertor Heat Removal Component in LHD Fabricated by Advanced Multi-Step Brazing (AMSB)

22. EUV/VUV Spectroscopy for the Study of Carbon Impurity Transport in Hydrogen and Deuterium Plasmas in the Edge Stochastic Magnetic Field Layer of Large Helical Device

23. Fusion product diagnostics based on commercially available chemical vapor deposition diamond detector in large helical device

24. Data-Driven Approach on the Mechanism of Radiative Collapse in the Large Helical Device

25. Data-Driven Control for Radiative Collapse Avoidance in Large Helical Device

26. Real-time wall conditioning and recycling modification utilizing boron and boron nitride powder injections into the Large Helical Device

27. Observation of a reduced-turbulence regime with boron powder injection in a stellarator

40. Three-dimensional structure of radiative cooling in impurity seeded plasmas in the Large Helical Device

41. Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device

42. Study of the effect of a closed divertor configuration on neutral particle control in the LHD plasma periphery

43. Investigation of heat flux deposition on divertor target on the Large Helical Device with EMC3-EIRENE modelling

44. Design Status of the Structural Components of the Helical Fusion Reactor FFHR-d1

45. Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors

46. Effects of Mild Baking on Hydrogen Removal from the Modified Surface of the First Wall in the LHD

47. Characterized divertor footprint profile modification with the edge pressure gradient in the Large Helical Device

48. Application of EMC3-EIRENE to Estimation of Influence of a Liquid Metal Limiter on an LHD-Type Fusion Plasma

49. Dust Formation from Arc Spots on Nanostructured Tungsten Surface

50. Tritium Balance in Large Helical Device during and after the First Deuterium Plasma Experiment Campaign

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