226 results on '"Missirlian, M."'
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2. Thermal and structural analysis of JT-60SA actively cooled divertor target submitted to high heat flux
3. Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST
4. Manufacturing, testing and installation of the full tungsten actively cooled ITER-like divertor in the WEST tokamak
5. HADES - high heat load testing - facility at CEA-IRFM
6. First heat flux estimation in the lower divertor of WEST with embedded thermal measurements
7. Postmortem assessment of the WEST Fiber Bragg grating and thermocouple diagnostic performances with HADES
8. Surface heat flux estimation with embedded thermocouples and Fiber Bragg Grating sensor in ITER-like plasma facing components
9. Emissivity measurement of the ITER-like plasma facing components of the WEST phase 2: Pre-exposure measurements and first WEST exposure
10. High heat flux testing of newly developed tungsten components for WEST
11. First temperature database achieved with Fiber Bragg Grating sensors in uncooled plasma facing components of the WEST lower divertor
12. Design and integration of femtosecond Fiber Bragg gratings temperature probes inside actively cooled ITER-like plasma-facing components
13. Performance assessment of thick W/Cu graded interlayer for DEMO divertor target
14. Development of Boron Coatings for antenna protection limiters in the WEST Tokamak
15. Thermomechanical simulation of flat tiles mock-ups under high heat flux
16. Tungsten coatings repair: An approach to increase the lifetime of plasma facing components
17. Effect of induction heating on flaw generation and expansion
18. Qualification and post-mortem investigation of actively cooled tungsten flat-tile mock-ups for WEST divertor
19. Mechanical analysis of WEST divertor support plate
20. Status on the W monoblock type high heat flux target with graded interlayer for application to DEMO divertor
21. Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components
22. Overview of the different processes of tungsten coating implemented into WEST tokamak
23. Measurements and controls implementation for WEST
24. Thermomechanical simulation of WEST actively cooled upper divertor
25. Evaluation of peak power flux densities based on full ion orbit calculation: Application to WEST ITER-like target
26. A fatigue lifetime assessment of WEST ITER Like Plasma Facing Unit
27. Reception tests of the WEST PFUs using ultrasonic testing and infrared thermography
28. Calculation of heat fluxes induced by radio frequency heating on the actively cooled protections of ion cyclotron resonant heating (ICRH) and lower hybrid (LH) antennas in Tore Supra
29. CEA contribution to the ITER ICRH antenna design
30. Status of the ITER Ion Cyclotron H&CD system
31. Characterization and damaging law of CFC for high heat flux actively cooled plasma facing components
32. Recent development toward the use of infrared thermography as a non destructive technique for defect detection in tungsten plasma facing components
33. Examination of high heat flux components for the ITER divertor after thermal fatigue testing
34. Influence of CFC quality on the performance of TS limiter elements under cyclic heat loading
35. Fatigue lifetime of repaired high heat flux components for ITER divertor
36. Engineering studies for the installation of an axi-symmetric metallic divertor in Tore Supra
37. High heat flux testing of mock-ups for a full tungsten ITER divertor
38. Manufacturing process and tests of a Lower Hybrid Passive–Active Multijunction launcher for long pulse experiments on Tore-Supra
39. Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing
40. Manufacturing process and tests of a lower hybrid passive active multi-junction launcher for long pulse experiments on Tore-Supra
41. Typology of defects in DEMO divertor target mockups
42. Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST
43. First feedback during series fabrication of ITER like divertor tungsten components for the WEST tokamak
44. Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST
45. In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak
46. Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements
47. Innovative image processing techniques applied to the thermographic inspection of PFC with SATIR facility
48. Thermal loads in gaps between ITER divertor monoblocks: First lessons learnt from WEST
49. Infrared images data merging for plasma-facing component inspection
50. Infrared thermography inspection methods applied to the target elements of W7-X divertor
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