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1. Lessons learned after three years of SPIDER operation and the first MITICA integrated tests

2. Overview of the TCV digital real-time plasma control system and its applications

3. Diagnostic data integration using deep neural networks for real-time plasma analysis

7. On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

9. An active feedback recovery technique from disruption events induced by m=2 n=1 tearing modes in ohmically heated tokamak plasmas

12. Highlights of recent SPIDER results and improvements

13. SPIDER, the Negative Ion Source Prototype for ITER: Overview of Operations and Cesium Injection

14. Lessons learned after three years of SPIDER operation and the first MITICA integrated tests

15. SPIDER in the roadmap of the ITER neutral beams

17. Status of the ITER remote experimentation centre

22. Highlights of recent SPIDER results and improvements

23. A substantial step forward in the realization of the ITER HNB system: The ITER NBI Test Facility

24. Diagnostics, data acquisition and control of the divertor test tokamak experiment

25. Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

27. Lessons learned after three years of SPIDER operation and the first MITICA integrated tests

30. SPIDER, the Negative Ion Source Prototype for ITER: Overview of Operations and Cesium Injection

31. On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

33. Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

38. First operations with caesium of the negative ion source SPIDER

39. Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X

41. Progress in the ITER neutral beam test facility

42. Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall

49. The ITER full size plasma source device design

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