345 results on '"Pégourié, B."'
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2. Proposal of a control scheme for testing a centrifuge-based pellet injection system in DIPAK-PET
3. Micron-sized dust and nanoparticles produced in the WEST tokamak
4. Numerical modelling of the impact of leakage under divertor baffle in WEST
5. Thermal stability and long term hydrogen/deuterium release from soft to hard amorphous carbon layers analyzed using in-situ Raman spectroscopy. Comparison with Tore Supra deposits
6. Long Term H-Release from Amorphous Carbon Evidenced by in Situ Raman Microscopy under Isothermal Heating
7. Raman study of CFC tiles extracted from the toroidal pump limiter of Tore Supra
8. Addressing the feasibility of inboard direct-line injection of high-speed pellets, for core fueling of DEMO
9. Final design of the JT-60SA pellet launching system for simultaneous density and ELM control
10. DEMO design using the SYCOMORE system code: Influence of technological constraints on the reactor performances
11. An innovative approach for DEMO core fuelling by inboard injection of high-speed pellets
12. Conceptual design status of the JT-60SA pellet launching system
13. Matter injection technology for DEMO, state of the art
14. Separatrix parameters and core performances across the WEST L-mode database
15. A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X
16. Evaluation of peak power flux densities based on full ion orbit calculation: Application to WEST ITER-like target
17. Safe and prolonged survival with long-term exposure to pomalidomide in relapsed/refractory myeloma
18. Tritium absorption and desorption in ITER relevant materials: comparative study of tungsten dust and massive samples
19. Modelling the erosion/deposition pattern of the Tore Supra Toroidal Pumped Limiter
20. Hydrogen trapping in carbon film: From laboratories studies to tokamak applications
21. Impact of leakage under divertor baffle on detachment onset in WEST
22. Multi-technique coupling for analysis of deuterium retention in carbon fiber composite NB31
23. Plasma physics and control studies planned in JT-60SA for ITER and DEMO operations and risk mitigation
24. Direct, spectroscopic measurement of electric fields in a plasma-RF antenna interaction region in Tore Supra
25. Confocal microscopy: A new tool for erosion measurements on large scale plasma facing components in tokamaks
26. Layer removal in gaps by laser process
27. Deuterium inventory in Tore Supra: Contribution of carbon deposits outgassing
28. Simultaneous deuterium implantation and ion beam microanalyses in CFC NB31: Understanding the in-bulk migration
29. Erosion–deposition mapping of the toroidal pump limiter of Tore Supra
30. Bifurcation to a stable limiter MARFE in Tore Supra
31. Deuterium inventory in Tore Supra: Coupled carbon–deuterium balance
32. Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation
33. Pellet core fueling in tokamaks, stellarators and reversed field pinches
34. Nuclear reaction and heavy ion ERD analysis of wall materials from controlled fusion devices: Deuterium and nitrogen-15 studies
35. Multi machine scaling of fuel retention in 4 carbon dominated tokamaks
36. Recent results on Ion Cyclotron Wall Conditioning in mid and large size tokamaks
37. Deuterium Inventory in Tore Supra (DITS): 2nd post-mortem analysis campaign and fuel retention in the gaps
38. Isotope exchange experiments on TEXTOR and TORE SUPRA using Ion Cyclotron Wall Conditioning and Glow Discharge Conditioning
39. Scaling of carbon erosion in Tore Supra
40. Structure of the carbon layers deposited on the toroidal pump limiter of Tore Supra
41. Post-disruption outgassing in Tore Supra
42. An overview of nuclear micro-beam analysis of surface and bulk fuel retention in carbon-fibre composites from Tore Supra
43. Raman study of CFC tiles extracted from the toroidal pump limiter of Tore Supra
44. Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing
45. Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST
46. Link between ablation and line emission for hydrogen fuelling pellet in LHD
47. RF wave coupling, plasma heating and characterization of induced plasma-material interactions in WEST L-mode discharges
48. Matter Injection in EU-DEMO: The Preconceptual Design
49. Measurements of scrape-off layer ion-to-electron temperature ratio in Tore Supra ohmic plasmas
50. Impurity production monitoring during RF experiments in Tore Supra
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