22 results on '"Missirlian, M."'
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2. Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST
3. First feedback during series fabrication of ITER like divertor tungsten components for the WEST tokamak
4. Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST
5. Development and application of W/Cu flat-type plasma facing components at ASIPP
6. Tungsten coating by ATC plasma spraying on CFC for WEST tokamak
7. Results of high heat flux qualification tests of W monoblock components for WEST
8. Wall surface temperature calculation in the SolEdge2D-EIRENE transport code
9. Study of the pores inside tungsten coating after thermal cycling for fusion device
10. Tungsten covered graphite and copper elements and ITER-like actively cooled tungsten divertor plasma facing units for the WEST project
11. The WEST project: validation program for WEST tungsten coated plasma facing components
12. Operational limits on WEST inertial divertor sector during the early phase experiment
13. Assessment of CFC grades under thermal fatigue for the ITER inner vertical target
14. Mechanical characterization of W-armoured plasma-facing components after thermal fatigue
15. The heat removal capability of actively cooled plasma-facing components for the ITER divertor
16. Micro-chemical analysis of high heat loaded CFC–Cu interfaces from Tore Supra and Wendelstein 7-X
17. Damage prediction of carbon fibre composite armoured actively cooled plasma-facing components under cycling heat loads
18. CFC/Cu bond damage in actively cooled plasma facing components
19. Qualification of high heat flux components: application to target elements of W7-X divertor
20. Fabrication and testing of W7-X pre-series target elements
21. Flat Tile Armour Cooled by Hypervapotron Tube: a Possible Technology for ITER
22. Typology of defects in DEMO divertor target mockups
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