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4. Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor

7. Changeover between helium and hydrogen fueled plasmas in JET and WEST

11. First heat flux estimation in the lower divertor of WEST with embedded thermal measurements

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

20. Measurements and controls implementation for WEST

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

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 * , **

34. Deuterium inventory in Tore Supra: Coupled carbon–deuterium balance

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

39. Multi machine scaling of fuel retention in 4 carbon dominated tokamaks

41. Recent results on Ion Cyclotron Wall Conditioning in mid and large size tokamaks

44. Scaling of carbon erosion in Tore Supra

45. ICRF physics aspects of wall conditioning with conventional antennas in large-size tokamaks

50. Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing

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