Zobrazeno 1 - 10
of 26
pro vyhledávání: '"M. J. Schaffer"'
Autor:
Cc Petty, Oliver Schmitz, A. W. Leonard, Ezekial A Unterberg, R.A. Moyer, P. B. Snyder, R. Laengner, J. G. Watkins, L. R. Baylor, T. W. Petrie, H. Stoschus, T. H. Osborne, T. L. Rhodes, T. E. Evans, M. J. Schaffer, J. S. Degrassie, K. H. Burrell, R. I. Pinsker, P. Gohil, Saskia Mordijck, J. A. Boedo, D. M. Orlov, M. W. Jakubowski, R. C. Wolf, M. E. Fenstermacher, C. J. Lasnier
Publikováno v:
Journal of Nuclear Materials. 415:S901-S905
As shown on DIII-D edge localized modes (ELMs) can be either completely eliminated or mitigated with resonant magnetic perturbation (RMP) fields. Two infrared cameras, separated 105° toroidally, were used to make simultaneous measurements of ELM hea
Autor:
T. H. Osborne, Saskia Mordijck, R.A. Moyer, J.A. Boedo, J. S. deGrassie, Oliver Schmitz, Anthony Leonard, Todd Evans, Keith H. Burrell, H. Frerichs, R. C. Wolf, M. J. Schaffer, P. Gohil, Detlev Reiter, M. E. Fenstermacher, M. W. Jakubowski, Larry R. Baylor, J. G. Watkins, C. J. Lasnier, Ezekial A Unterberg, U. Samm
Publikováno v:
Contributions to Plasma Physics. 50:701-707
Stochastic boundaries in fusion devices have been investigated in tokamaks, stellarators and reversed field pinch experiments for many years. However, since edge localized modes (ELMs) have been successfully eliminated in H-mode plasmas at the DIII-D
Autor:
M. J. Schaffer, P. B. Parks
Publikováno v:
Physics of Plasmas. 10:1411-1423
This paper reports on the interchange stability of a realistic analytical equilibrium solution of a field-reversed configuration (FRC) contained within a tight fitting cylindrical flux conserver with end walls, no external flux, and arbitrary elongat
Publikováno v:
Physics of Plasmas. 8:4463-4469
The field-reversed configuration (FRC) is a high-beta compact toroidal plasma confinement scheme in which the external poloidal field is reversed on the geometric axis by azimuthal (toroidal) plasma current. A quasineutral, hybrid, particle-in-cell (
Autor:
George McKee, M.E. Friend, S.L. Allen, R. J. Jayakumar, R.C. Isler, T. W. Petrie, N.H. Brooks, P.C. Stangeby, G.D. Porter, R.J. Colchin, M.E. Fenstermacher, J.G. Watking, N. S. Wolf, Anthony Leonard, M. J. Schaffer, T.H. Osborne, R.A. Moyer, J.A. Boedo, A. S. Bozek, C.J. Lasnier, A. T. Ramsey, R.C. O'Neill, T.N. Carlstrom, Rajesh Maingi, Dennis Whyte, M. Murakami, M. A. Mahdavi, M. R. Wade, T.E. Evans, T. A. Casper, W. P. West, R.D. Stambaugh
Publikováno v:
Journal of Nuclear Materials. :995-1001
We present the results from DIII-D experiments and modeling focused on the divertor issues of an `Advanced Tokamak' (AT). Operation at high plasma pressure β with good energy confinement H requires core and divertor plasma shaping and current profil
Autor:
R Raman, T R Jarboe, D Mueller, M J Schaffer, R Maqueda, B A Nelson, S Sabbagh, M Bell, R Ewig, E Fredrickson, D Gates, J Hosea, H Ji, R Kaita, S M Kaye, H Kugel, R Maingi, J Menard, M Ono, D Orvis, F Paoletti, S Paul, M Peng, C H Skinner, J B Wilgen, S Zweben, the NSTX Research Team
Publikováno v:
Plasma Physics and Controlled Fusion. 43:305-312
Coaxial helicity injection has been investigated on the National Spherical Torus Experiment (NSTX). Initial experiments produced 130 kA of toroidal current without the use of the central solenoid. The corresponding injector current was 20 kA. Dischar
Autor:
T. Hutter, B. Pégourié, C. Grisolia, M. R. Wade, A. Grosman, Taner Uckan, T. Loarer, Ph. Ghendrih, Larry W Owen, C. Christopher Klepper, Dongkyu Lee, M.A. Mahdavi, P.K. Mioduszewski, M J Schaffer, M. Chatelier, C. E. Thomas, Rajesh Maingi, D. L. Hillis, M.M. Menon, J.T. Hogan
Publikováno v:
Scopus-Elsevier
Particle control is playing an increasingly important role in tokamak plasma performance. The present paper discusses particle control of hydrogen/deuterium by wall pumping on graphite or carbonized surfaces, as well as by external exhaust with pumpe
Autor:
G J Kramer, R Ellis, M Gorelenkova, W W Heidbrink, T Kurki-Suonio, R Nazikian, A Salmi, M J Schaffer, K Shinohara, J A Snipes, D A Spong, T Koskela
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::70c061ce231f16f68f9e894165d6dbb0
https://doi.org/10.2172/1025018
https://doi.org/10.2172/1025018
Autor:
P.K. Mioduszewski, G. Haas, J.T. Hogan, D. N. Hill, T.E. Evans, C. Christopher Klepper, Rajesh Maingi, J.G. Gilligan, D. Buchenauer, M. J. Schaffer, M. Ali Mahdavi, Larry W Owen, T. W. Petrie, G. L. Jackson
Publikováno v:
Journal of Nuclear Materials. :1090-1095
The DIII-D divertor baffle system was designed to facilitate density control in long pulse H-mode discharges by removing a particle flux equal to the neutral beam fueling rate (∼20 Torrl/s) with a ∼1 mTorr neutral pressure under the baffle (p0).