93 results on '"Whyte, D.G."'
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2. Assessment of X-point target divertor configuration for power handling and detachment front control
3. Initial results of tests of depth markers as a surface diagnostic for fusion devices
4. Experimental investigation on the effect of surface electric field in the growth of tungsten nano-tendril morphology due to low energy helium irradiation
5. ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets
6. Dynamic measurement of the helium concentration of evolving tungsten nanostructures using Elastic Recoil Detection during plasma exposure
7. Characterizing the recovery of a solid surface after tungsten nano-tendril formation
8. Fusion materials science and technology research opportunities now and during the ITER era
9. A lithium depth-marker technique for rapid erosion and deposition measurements
10. Internal physics of the ion-sensitive probe
11. Helium concentration in tungsten nano-tendril surface morphology using Elastic Recoil Detection
12. Investigation of RF-enhanced plasma potentials on Alcator C-Mod
13. Constraining the divertor heat width in ITER
14. Heat-flux footprints for I-mode and EDA H-mode plasmas on Alcator C-Mod
15. Comparison of tungsten nano-tendrils grown in Alcator C-Mod and linear plasma devices
16. Helium effects on tungsten under fusion-relevant plasma loading conditions
17. Reactor similarity for plasma–material interactions in scaled-down tokamaks as the basis for the Vulcan conceptual design
18. Vulcan: A steady-state tokamak for reactor-relevant plasma–material interaction science
19. The lower hybrid current drive system for steady-state operation of the Vulcan tokamak conceptual design
20. Global particle balance measurements in DIII-D H-mode discharges
21. A study of tungsten migration in the Alcator C-Mod divertor
22. Quantification of chemical erosion in the DIII-D divertor and implications for ITER
23. Interpretation and implementation of an ion sensitive probe as a plasma potential diagnostic on Alcator C-Mod
24. The scaling of fuel recovered following un-mitigated disruptions in Alcator C-Mod with high-Z PFCs
25. Analysis of C-MOD molybdenum divertor erosion and code/data comparison
26. High heat flux components—Readiness to proceed from near term fusion systems to power plants
27. ICRF specific impurity sources and plasma sheaths in Alcator C-Mod
28. On the consequences of neutron induced damage for volumetric fuel retention in plasma facing materials
29. Measurement of hydrogenic retention and release in molybdenum with the DIONISOS experiment
30. Indications of an inward pinch in the inner SOL of DIII-D from 13C deposition experiments
31. Characterization of chemical sputtering using the Mark II DiMES porous plug injector in attached and semi-detached divertor plasmas of DIII-D
32. Disruption mitigation on Alcator C-Mod using high-pressure gas injection: Experiments and modeling toward ITER
33. Influence of boronization on operation with high-Z plasma facing components in Alcator C-Mod
34. Particle flux and radial profiles in the SOL of DIII-D during ELMing H-mode
35. Dynamics of hydrogenic retention in molybdenum: First results from DIONISOS
36. Hydrogen and helium trapping in tungsten under simultaneous irradiations
37. OEDGE modeling of the DIII-D H-mode 13CH4 puffing experiment
38. Spectroscopic characterization and simulation of chemical sputtering using the DiMES porous plug injector in DIII-D
39. Transport and deposition of 13C from methane injection into partially detached H-mode plasmas in DIII-D
40. Mixed-material layer formation on graphite exposed to deuterium plasmas containing beryllium
41. Re-construction of detached divertor plasma conditions in DIII-D using spectroscopic and probe data
42. 13C transport studies in L-mode divertor plasmas on DIII-D
43. OEDGE modeling of 13C deposition in the inner divertor of DIII-D
44. Tritium recovery in ITER by radiative plasma terminations
45. DIVIMP modeling of the toroidally symmetrical injection of 13CH4 into the upper SOL of DIII-D
46. Far scrape-off layer and near wall plasma studies in DIII-D
47. Measured signatures of low energy, physical sputtering in the line shape of neutral carbon emission
48. Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor
49. Advanced tokamak operation using the DIII–D plasma control system
50. Effect of cyclic extremely high loads on behaviour of the ATJ graphite sample exposed to DIII-D divertor plasma
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