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1. Plasma-wall interaction impact of the ITER re-baseline

2. Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

3. Overview of T and D–T results in JET with ITER-like wall

4. Fuelling of deuterium–tritium plasma by peripheral pellets in JET experiments

5. Assessment of plasma power deposition on the ITER ICRH antennas

6. Global scaling of the heat transport in fusion plasmas

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

8. Fusion power predictions for β N ≈ 1.8 baseline scenario with 50–50 D–T fuel mix and NBI injection in preparation to D–T operations at JET

9. JINTRAC integrated simulations of ITER scenarios including fuelling and divertor power flux control for H, He and DT plasmas

10. Assessment of plasma power deposition on the ITER ICRH antennas

11. Constructing a new predictive scaling formula for ITER's divertor heat-load width informed by a simulation-anchored machine learning

12. Overview of first Wendelstein 7-X high-performance operation

13. Pellet fueling experiments in Wendelstein 7-X

14. Integrated core-SOL modelling of fuelling, density control and divertor heat loads for the flat-top phase of the ITER H-mode D-T plasma scenarios

15. Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control

16. Modelling one-third field operation in the ITER pre-fusion power operation phase

17. EU DEMO transient phases: Main constraints and heating mix studies for ramp-up and ramp-down

18. Overview of the JET results in support to ITER

19. Self-consistent Plasma Simulations of the ITER inductive scenario

20. Current ramps in tokamaks: from present experiments to ITER scenarios

21. Considerations on the DEMO pellet fuelling system

22. Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER

23. Current rise studies at ASDEX Upgrade and JET in preparation for ITER

24. EFD-P(13)48 Modelling of JET Hybrid Scenarios with GLF23 Transport Model: E¥B Shear Stabilization of Anomalous Transport

25. EFD-P(13)01 Numerical Analysis of JET Discharges with the European Transport Simulator

26. EFD-P(13)32 Modelling the Ohmic L-mode Ramp-down Phase of JET Hybrid Pulses Using JETTO with Bohm-Gyro-Bohm Transport

27. Numerical analysis of JET discharges with the European Transport Simulator

28. ELM pacing and trigger investigations at JET with the new ITER-like wall

29. Analysis of fuelling requirements in ITER H-modes with SOLPS-EPED1 derived scalings

30. Modelling the Ohmic L-mode ramp-down phase of JET hybrid pulses using JETTO with Bohm–gyro-Bohm transport

31. ELM pacing investigations at JET with the new pellet launcher

32. Understanding of the fundamental differences in JET and JT-60U AT discharges

33. Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITERa)

34. Cross-field dynamics of the homogenization of the pellet deposited material in Tore Supra

35. Simulations of density profiles, pellet fuelling and density control in ITER

36. Modelling of the JET current ramp-up experiments and projection to ITER

37. Observation and analysis of pellet material ∇B drift on MAST

38. Influence of the low order rational q surfaces on the pellet deposition profile

39. Recent results on the fuelling and control of plasmas by pellet injection, application to ITER

40. Experimental studies of ITER demonstration discharges

41. Integrated modelling of ITER reference scenarios

42. Blower Gun pellet injection system for W7-X

43. Enhanced energy confinement after series of pellets in Wendelstein 7-X.

44. Modelling one-third field operation in the ITER pre-fusion power operation phase.

45. Control of the hydrogen:deuterium isotope mixture using pellets in JET.

46. Pellet fueling experiments in Wendelstein 7-X.

47. The CRONOS suite of codes for integrated tokamak modelling

48. Overview of JET results for optimising ITER operation

49. Integrated core-SOL modelling of fuelling, density control and divertor heat loads for the flat-top phase of the ITER H-mode D-T plasma scenarios.

50. (Expected difficulties with) density-profile control in W7-X high-performance plasmas.

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