Results 41 to 50 of about 3,538 (193)

Micro-tearing modes in spherical and conventional tokamaks

, 2013
The onset and characteristics of Micro-Tearing Modes (MTM) in the core of spherical (NSTX) and conventional tokamaks (ASDEX-UG and JET) are studied through local linear gyrokinetic simulations with gyro [J. Candy and E.
Fülöp, T., Guttenfelder, W., Mollén, A., Moradi, S., Pusztai, I.   +4 more
core   +1 more source

Two-dimensional imaging of edge-localized modes in KSTAR plasmas unperturbed and perturbed by n=1 external magnetic fields [PDF]

, 2019
The temporal evolution of edge-localized modes (ELMs) has been studied using a 2-D electron cyclotron emission imaging system in the KSTAR tokamak.
Domier, CW, Donne, AJH, Jeon, YM, Lee, J, Lee, JH, Luhmann, NC, Min-June Choi, Park, HK, Tobias, B, Woochang Lee, Yoon, SW, Yun, GS   +11 more
core   +1 more source

In search of X-point radiator regime features in NSTX and DIII-D discharges with the snowflake divertor

Nuclear Materials and Energy
Experimental data from NSTX and DIII-D discharges with the snowflake (SF) divertor configurations are analyzed toward the development of the X-point radiator (XPR) concept. The XPR divertor regime was recently realized in standard divertor configurations
V.A. Soukhanovskii, S.L. Allen, M.E. Fenstermacher, C.J. Lasnier, A.G. McLean, F. Scotti, E. Kolemen, A. Diallo, S. Gerhardt, S. Kaye, B.P. LeBlanc, R. Maingi, J.E. Menard, R. Raman, A.W. Hyatt, A.W. Leonard, T.H. Osborne   +16 more
doaj   +1 more source

NSTX-U research advancing the physics of spherical tokamaks

Nuclear Fusion
The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low- A , high beta plasmas to lower collisionality levels, understanding of the transport mechanisms that set ...
J.W. Berkery, P.O. Adebayo-Ige, H. Al Khawaldeh, G. Avdeeva, S-G. Baek, S. Banerjee, K. Barada, D.J. Battaglia, R.E. Bell, E. Belli, E.V. Belova, N. Bertelli, N. Bisai, P.T. Bonoli, M.D. Boyer, J. Butt, J. Candy, C.S. Chang, C.F. Clauser, L.D. Corona Rivera, M. Curie, P.C. de Vries, R. Diab, A. Diallo, J. Dominski, V.N. Duarte, E.D. Emdee, N.M. Ferraro, R. Fitzpatrick, E.L. Foley, E. Fredrickson, M.E. Galante, K.F. Gan, S. Gerhardt, R. Goldston, W. Guttenfelder, R. Hager, M.O. Hanson, S.C. Jardin, T.G. Jenkins, S.M. Kaye, A. Khodak, J. Kinsey, A. Kleiner, E. Kolemen, S. Ku, M. Lampert, B. Leard, B.P. LeBlanc, J.B. Lestz, F.M. Levinton, C. Liu, T. Looby, R. Lunsford, T. Macwan, R. Maingi, J. McClenaghan, J.E. Menard, S. Munaretto, M. Ono, A. Pajares, J. Parisi, J-K. Park, M.S. Parsons, B.S. Patel, Y.V. Petrov, M. Podestà, F. Poli, M. Porcelli, T. Rafiq, S.A. Sabbagh, Á. Sánchez Villar, E. Schuster, J. Schwartz, A. Sharma, S. Shiraiwa, P. Sinha, D. Smith, S. Smith, V.A. Soukhanovskii, G. Staebler, E. Startsev, B. Stratton, K.E. Thome, W. Tierens, M. Tobin, I.U. Uzun-Kaymak, B. Van Compernolle, J. Wai, W. Wang, W. Wehner, A. Welander, J. Yang, V. Zamkovska, X. Zhang, X.L. Zhu, S. Zweben   +96 more
doaj   +1 more source

Full-$f$ gyrokinetic simulation of turbulence in a helical open-field-line plasma

, 2018
Curvature-driven turbulence in a helical open-field-line plasma is investigated using electrostatic five-dimensional gyrokinetic continuum simulations in an all-bad-curvature helical-slab geometry.
Hakim, Ammar, Hammett, Gregory W., Shi, Eric L., Stoltzfus-Dueck, Timothy   +3 more
core   +1 more source

There is no standard model of ZFC [PDF]

, 2018
Main results are:(i) Let M_st be standard model of ZFC. Then ~Con(ZFC+∃M_st), (ii) let k be an inaccessible cardinal then ~Con(ZFC+∃k),[10],11]
Foukzon, Jaykov
core  

2D full-wave simulation of waves in space and tokamak plasmas

EPJ Web of Conferences, 2017
Simulation results using a 2D full-wave code (FW2D) for space and NSTX fusion plasmas are presented. The FW2D code solves the cold plasma wave equations using the finite element method.
Kim Eun-Hwa, Bertelli Nicola, Johnson Jay, Valeo Ernest, Hosea Joel   +4 more
doaj   +1 more source

Toroidal asymmetries in divertor impurity influxes in NSTX

Nuclear Materials and Energy, 2017
Toroidal asymmetries in divertor carbon and lithium influxes were observed in NSTX, due to toroidal differences in surface composition, tile leading edges, externally-applied three-dimensional (3D) fields and toroidally-localized edge plasma ...
F. Scotti, V.A. Soukhanovskii, J.-W. Ahn, A.G. McLean, R. Kaita   +4 more
doaj   +1 more source

Comparing lithium vapor box designs in a high heat flux scenario using SOLPS-ITER

Nuclear Materials and Energy, 2023
SOLPS calculations of lithium vapor box divertor designs on NSTX-U are presented. Predictive high power simulations (Pheat=10 MW, qpeakunmitigated∼65 MW/m2) are used to compare and contrast two divertor designs.
E.D. Emdee, R.J. Goldston
doaj   +1 more source

Rogowski Loop design for NSTX [PDF]

, 2000
The Rogowski Loop is one of the most basic diagnostics for tokamak operations. On the National Spherical Torus Experiment (NSTX), the plasma current Rogowski Loop had the constraints of the very limited space available on the center stack, 5,000 volt isolation, flexibility requirements as it remained a part of the Center Stack assembly after the first ...
McCormack, B., Kaita, R., Kugel, H., Hatcher, R.   +3 more
openaire   +2 more sources