277 results on '"Kugel, H.W."'
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2. Dependence of recycling and edge profiles on lithium evaporation in high triangularity, high performance NSTX H-mode discharges
3. Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance
4. Plasma facing surface composition during NSTX Li experiments
5. Characterization of fueling NSTX H-mode plasmas diverted to a liquid lithium divertor
6. Measurement and modeling of surface temperature dynamics of the NSTX liquid lithium divertor
7. Observation of non-Maxwellian electron distributions in the NSTX divertor
8. Recent progress of NSTX lithium program and opportunities for magnetic fusion research
9. Modification of the electron energy distribution function during lithium experiments on the National Spherical Torus Experiment
10. NSTX plasma operation with a Liquid Lithium Divertor
11. Observation and modeling of inner divertor re-attachment in discharges with lithium coatings in NSTX
12. NSTX plasma response to lithium coated divertor
13. Measurements and 2-D modeling of recycling and edge transport in discharges with lithium-coated PFCs in NSTX
14. Reduction of low-Z impurities during plasma start-up
15. Simulations of diffusive lithium evaporation onto the NSTX vessel walls
16. Surface chemistry and physics of deuterium retention in lithiated graphite
17. Deuterium retention in NSTX with lithium conditioning
18. “Snowflake” divertor configuration in NSTX
19. Implications of NSTX lithium results for magnetic fusion research
20. Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation
21. Physics design requirements for the National Spherical Torus Experiment liquid lithium divertor
22. Measurement of lithium and deuterium on NSTX carbon tiles
23. Mass changes in NSTX surface layers with Li conditioning as measured by quartz microbalances
24. Evaporated lithium surface coatings in NSTX
25. Experimental studies of lithium-based surface chemistry for fusion plasma-facing materials applications
26. Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces
27. On the secular density rises in NBI-heated H-mode plasmas in NSTX
28. Measurements of accumulated metallic impurities during LiTER operation in NSTX
29. Effect of lithium PFC coatings on NSTX density control
30. Divertor heat flux reduction and detachment experiments in NSTX
31. Pulse-by-pulse measurements of dynamic retention and deposition in NSTX
32. Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment
33. Results of NSTX heating experiments
34. Accounting of the power balance for neutral-beam heated H-mode plasmas in NSTX
35. ELMs and the H-mode pedestal in NSTX
36. Divertor regimes in NSTX
37. Development of NSTX particle control techniques
38. Heat flux scaling experiments in NSTX
39. Impact of the wall conditioning program on plasma performance in NSTX
40. Core fueling and edge particle flux analysis in ohmically and auxiliary heated NSTX plasmas
41. Remote metrology, mapping, and motion sensing of plasma facing components using FM coherent laser radar
42. Overview of impurity control and wall conditioning in NSTX
43. Characteristics of the First H-mode Discharges in NSTX
44. Neutron Activation Cool-down of the Tokamak Fusion Test Reactor
45. Development of lithium deposition techniques for TFTR
46. Versatile TV system for PBX-M plasma control
47. TFTR radiation contour and shielding efficiency measurements during D-D operations
48. Real-time boronization in PBX-M using erosion of solid boronized targets
49. Measurements of TFTR D-T radiation shielding efficiency
50. Impurity behavior during ion-Bernstein wave heating in PBX-M
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