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1. Hollow pellet injection for magnetic fusion

2. Summary of the FESAC Transformative Enabling Capabilities Panel Report

5. Total Fluid Pressure Imbalance in the Scrape-Off Layer of Tokamak Plasmas

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

7. NSTX-U research advancing the physics of spherical tokamaks

8. Estimates of global recycling coefficients for LTX-β discharges

9. Overview of NSTX Upgrade initial results and modelling highlights

14. An overview of recent physics results from NSTX

16. High flux expansion divertor studies in NSTX

17. Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

20. Overview of physics results from the conclusive operation of the National Spherical Torus Experiment

21. Improved understanding of physics processes in pedestal structure, leading to improved predictive capability for ITER

22. Overview of physics results from NSTX

23. Advances in high-harmonic fast wave physics in the National Spherical Torus Experimenta)

24. Overview of results from the National Spherical Torus Experiment (NSTX)

27. Overview of recent physics results from the National Spherical Torus Experiment (NSTX)

28. A 'multi-colour' SXR diagnostic for time and space-resolved measurements of electron temperature, MHD activity and particle transport in MCF plasmas

29. Effect of plasma shaping on performance in the National Spherical Torus Experimenta)

30. Progress towards steady state on NSTX

31. Enhanced performance in fusion plasmas through turbulence suppression by megaelectronvolt ions

33. Enhanced performance in fusion plasmas through turbulence suppression by megaelectronvolt ions

34. Progress towards high-performance, steady-state spherical torus

35. The national spherical torus experiment (NSTX) research programme and progress towards high beta, long pulse operating scenarios

37. Achievement of ion temperatures in excess of 100 million degrees Kelvin in the compact high-field spherical tokamak ST40

39. Overview of Liquid-Metal PFC R&D at the University of Illinois Urbana-Champaign

40. Higher fusion power gain with profile control in DIII-D tokamak plasmas

41. Stability in high gain plasmas in DIII-D*

42. Local analysis of confinement and transport in neutral beam heated DIII-D discharges with negative magnetic shear

43. Higher Fusion Power Gain with Current and Pressure Profile Control in Strongly Shaped DIII-D Tokamak Plasmas

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