374 results on '"Tsitrone, E"'
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2. Survey of tungsten gross erosion from main plasma facing components in WEST during a L-mode high fluence campaign
3. Thermal and statistical analysis of the high-Z tungsten-based UFOs observed during the first deuterium high fluence campaign of the WEST tokamak
4. Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor
5. Dust collection after the high fluence campaign of the WEST tokamak
6. Utilization of boron particulate wall conditioning in the full tungsten environment of WEST
7. Changeover between helium and hydrogen fueled plasmas in JET and WEST
8. Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak
9. Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES
10. Edge cracking of WEST tungsten actively cooled plasma facing components after plasma operation
11. First heat flux estimation in the lower divertor of WEST with embedded thermal measurements
12. Interpretation of temperature distribution observed on W-ITER-like PFUs in WEST monitored with a very-high-resolution IR system
13. Evolution of pre-damaged ITER grade plasma facing components under WEST plasma exposure: smoothing and tungsten sources.
14. Remote experiment with WEST from ITER Remote Experimentation Centre
15. Raman study of CFC tiles extracted from the toroidal pump limiter of Tore Supra
16. Comparison of ion cyclotron wall conditioning discharges in hydrogen and helium in JET
17. Testing of ITER-grade Plasma Facing Units in the WEST tokamak: progress in understanding heat loading and damage mechanisms
18. Micron-sized dust and nanoparticles produced in the WEST tokamak
19. Overview of the different processes of tungsten coating implemented into WEST tokamak
20. Measurements and controls implementation for WEST
21. H-mode WEST tungsten divertor operation: deuterium and nitrogen seeded simulations with SOLEDGE2D-EIRENE
22. Evaluation of peak power flux densities based on full ion orbit calculation: Application to WEST ITER-like target
23. Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
24. Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns
25. Assessment of tungsten sources in the edge plasma of WEST
26. Research status and issues of tungsten plasma facing materials for ITER and beyond
27. The WEST project: Current status of the ITER-like tungsten divertor
28. The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment
29. Emissivity measurement of the ITER-like plasma facing components of the WEST phase 2: Pre-exposure measurements and first WEST exposure
30. Characterizing W sources in the all-W wall, all-RF WEST tokamak environment * , **
31. Confocal microscopy: A new tool for erosion measurements on large scale plasma facing components in tokamaks
32. Layer removal in gaps by laser process
33. Erosion–deposition mapping of the toroidal pump limiter of Tore Supra
34. Deuterium inventory in Tore Supra: Coupled carbon–deuterium balance
35. Comparison of long term fuel retention in JET between carbon and the ITER-Like Wall
36. Tungsten sources and core contamination in WEST plasmas: from experiments to simulations
37. Overview of the emissivity measurements performed in WEST: in situ and post-mortem observations
38. Fuel retention study in fusion reactor walls by micro-NRA deuterium mapping
39. Multi machine scaling of fuel retention in 4 carbon dominated tokamaks
40. Assessment of massive gas injection as a disruption mitigation tool in Tore Supra
41. Recent results on Ion Cyclotron Wall Conditioning in mid and large size tokamaks
42. Deuterium Inventory in Tore Supra (DITS): 2nd post-mortem analysis campaign and fuel retention in the gaps
43. Isotope exchange experiments on TEXTOR and TORE SUPRA using Ion Cyclotron Wall Conditioning and Glow Discharge Conditioning
44. Scaling of carbon erosion in Tore Supra
45. ICRF physics aspects of wall conditioning with conventional antennas in large-size tokamaks
46. Structure of the carbon layers deposited on the toroidal pump limiter of Tore Supra
47. Post-disruption outgassing in Tore Supra
48. An overview of nuclear micro-beam analysis of surface and bulk fuel retention in carbon-fibre composites from Tore Supra
49. Optimization of laser ablation technique for deposited layer removal on carbon plasma facing components
50. Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing
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