Rajesh Maingi

Best Publications

• Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

  T. Eich;A.W. Leonard;R.A. Pitts;W. Fundamenski

  654
  Citations

• Exploration of spherical torus physics in the NSTX device

  M. Ono;S.M. Kaye;Y.-K.M. Peng;G. Barnes

  541
  Citations

• A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak

  J. Li;H. Y. Guo;H. Y. Guo;B. N. Wan;X. Z. Gong

  309
  Citations

• Pedestal stability comparison and ITER pedestal prediction

  P.B. Snyder;N. Aiba;M.N.A. Beurskens;R.J. Groebner

  290
  Citations

• Edge-localized-mode suppression through density-profile modification with lithium-wall coatings in the National Spherical Torus Experiment.

  R. Maingi;T. H. Osborne;B. P. LeBlanc;R. E. Bell

  229
  Citations

• The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment

  H. W. Kugel;M. G. Bell;J.-W. Ahn;J. P. Allain

  216
  Citations

• Resistive wall stabilized operation in rotating high beta NSTX plasmas

  S. A. Sabbagh;A. C. Sontag;J. Bialek;D. A. Gates

  204
  Citations

• Fusion nuclear science facilities and pilot plants based on the spherical tokamak

  J.E. Menard;T. Brown;L. El-Guebaly;M. Boyer

  194
  Citations

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

  C.S. Chang;S. Ku;A. Loarte;V. Parail

  179
  Citations

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

  E. A. Lazarus;G. A. Navratil;C. M. Greenfield;E. J. Strait

  174
  Citations

• Confinement and local transport in the National Spherical Torus Experiment (NSTX)

  S.M. Kaye;F.M. Levinton;D. Stutman;K. Tritz

  159
  Citations

• Enhanced H-mode pedestals with lithium injection in DIII-D

  T.H. Osborne;G.L. Jackson;Z. Yan;R. Maingi

  157
  Citations

• Edge turbulence measurements in NSTX by gas puff imaging

  R. J. Maqueda;G. A. Wurden;S. Zweben;L. Roquemore

  156
  Citations

• THE ARIES-CS COMPACT STELLARATOR FUSION POWER PLANT

  F. Najmabadi;A. R. Raffray;S. I. Abdel-Khalik;L. Bromberg

  156
  Citations

• Analysis of a multi-machine database on divertor heat fluxesa)

  M. A. Makowski;D. Elder;T. K. Gray;B. LaBombard

  150
  Citations

• The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment

  R. Maingi;D. P. Boyle;D. P. Boyle;J. M. Canik;S. M. Kaye

  146
  Citations

• Pedestal conditions for small ELM regimes in tokamaks

  N. Oyama;P. Gohil;L. D. Horton;A. E. Hubbard

  134
  Citations

• Physics design of the national spherical torus experiment

  Stanley M. Kaye;Masayuki Ono;Yueng-Kay Martin Peng;Donald B. Batchelor

  129
  Citations

• New steady-state quiescent high-confinement plasma in an experimental advanced superconducting tokamak.

  J. S. Hu;Z. Sun;H. Y. Guo;H. Y. Guo;J. G. Li

  129
  Citations

• Overview of the physics and engineering design of NSTX upgrade

  J. Menard;J. Caniky;J. Chrzanowski;M. Denault

  11
  Citations