105 results on '"Mitteau, R."'
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2. Calibration methods and uncertainties estimation of WEST infrared thermography diagnostics
3. The wide-angle infrared diagnostic for the first wall monitoring of the WEST tokamak
4. High heat flux performance assessment of ITER enhanced heat flux first wall technology after neutron irradiation
5. WEST operation with real time feed back control based on wall component temperature toward machine protection in a steady state tungsten environment
6. On the hydraulic behaviour of ITER Shield Blocks #14 and #08. Computational analysis and comparison with experimental tests
7. The combined effects of magnetic asymmetry, assembly and manufacturing tolerances on the plasma heat load to the ITER first wall
8. A full tungsten divertor for ITER: Physics issues and design status
9. Physics basis and design of the ITER plasma-facing components
10. A shaped First Wall for ITER
11. ITER plasma-facing components
12. Heat loads and shape design of the ITER first wall
13. Mechanical design features and challenges for the ITER ICRH antenna
14. A Geometrical approach to evaluating the heat flux peaking factor on first wall components
15. Analysis for shaping the ITER first wall
16. Study of heat flux deposition on the limiter of the Tore Supra tokamak
17. Power deposition modelling of the ITER-like wall beryllium tiles at JET
18. Analysis of radiative disruptions in RF-heated Tore Supra plasmas using infrared imaging
19. Spatially resolved charge exchange flux calculations on the Toroidal Pumped Limiter of Tore Supra
20. Tungsten coatings for the JET ITER-like wall project
21. Surface modification and hydrogen isotope retention in CFC during plasma irradiation in the Tore Supra tokamak
22. Simulations of ITER start-up and assessment of limiter power loads
23. A possible method of carbon deposit mapping on plasma facing components using infrared thermography
24. Model for impurity generation, transport and deposition in the complex CIEL environment
25. Processing of tungsten/copper materials from W–CuO powder mixtures
26. R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project
27. Recent developments toward the use of tungsten as armour material in plasma facing components
28. RF heating optimization on Tore Supra using feedback control of infrared measurements
29. Experience gained from high heat flux actively cooled PFCs in Tore Supra
30. Role of wall implantation of charge exchange neutrals in the deuterium retention for Tore Supra long discharges
31. Modelling of heat deposition onto the Tore Supra toroidal pumped limiter
32. Steady state heat exhaust in Tore Supra: operational safety and edge parameters
33. Hot spot effect on infrared spectral luminance emitted by carbon under plasma particles impact
34. High heat flux components in fusion devices: from current experience in Tore Supra towards the ITER challenge
35. Effects of supra-thermal particle impacts on Tore Supra plasma facing components
36. Heat flux pattern on the toroidal pump limiter of Tore Supra: first observations and preliminary analysis
37. Design of an improved vacuum vessel protection for very long pulse operation in Tore Supra
38. Design criteria for Tore Supra high heat flux components
39. Analysis of an in-service rupture of the inner first wall of tore supra
40. Self-shadowing, gaps and leading edges on Tore Supra's inner first wall
41. Active cooling, calorimetry and energy balance in Tore Supra
42. Long discharges in a steady state with D2 and N2 on the actively cooled tungsten upper divertor in WEST.
43. Power deposition and margins on the Tore Supra pump limiter and fabrication of the high heat flux components
44. Heat flux deposition on plasma-facing components using a convective model with ripple and Shafranov shift
45. Limiter heat load and consequences on impurity source and transport
46. ITER blanket engineering challenges and solutions.
47. High heat flux testing impact on the Tore Supra toroidal pumped limiter achievement.
48. The Tore Supra toroidal pump limiter: experience feedback of HHF elements series manufacture.
49. Design and manufacture of the Toroidal Pump Limiter-start up version for the CIEL project.
50. The ITER blanket system design challenge.
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