论文信息 - Physics design of the national spherical torus experiment - 字舞流文

Physics design of the national spherical torus experiment

The mission of the National Spherical Torus Experiment (NSTX) is to prove the principles of spherical torus physics by producing high-beta toroidal plasmas that are non-inductively sustained, and whose current profiles are in steady-state. NSTX will be one of the first ultra low a[P(input) up to 11 MW] in order to produce high-beta toroidal (25 to 40%), low collisionality, high bootstrap fraction (less than or equal to 70%) discharges. Both radio-frequency (RF) and neutral-beam (NB) heating and current drive will be employed. Built into NSTX is sufficient configurational flexibility to study a range of operating space and the resulting dependences of the confinement, micro- and MHD stability, and particle and power handling properties. NSTX research will be carried out by a nationally based science team.

M. Ono | Yong-Seok Hwang | Neil Pomphrey | Henry W. Kugel | Richard Majeski | Stephen C. Jardin | Charles Kessel | Robert J. Goldston | Dennis J Strickler | Mark Dwain Carter | Rajesh Maingi | Wonho Choe | Thomas R. Jarboe | Franco Paoletti | Brian A. Nelson | D. W. Johnson | E. J. Synakowski | Steven Anthony Sabbagh | Stanley M. Kaye | Donald B. Batchelor | Jonathan Menard | Robert Kaita | David Mikkelsen | D. Strickler | James R. Wilson | S. Jardin | C. Kessel | E. Synakowski | D. Batchelor | G. Rewoldt | M. Carter | H. Kugel | R. Kaita | R. Majeski | W. Choe | R. Goldston | N. Pomphrey | D. Mikkelsen | S. Sabbagh | S. Kaye | J. Menard | B. Nelson | D. Johnson | R. Maingi | M. Ono | F. Paoletti | T. Jarboe | Y. Hwang | David W. Johnson | David J. Orvis | Yueng-Kay Martin Peng | E. Fred Jaeger | Janhardan Manickam | Gregory Rewoldt | D. Orvis | J. Manickam | E. Jaeger | Y. Peng

[1] Dennis J Strickler,et al. Features of spherical torus plasmas , 1986 .

[2] J. E. RICE,et al. Observations of central toroidal rotation in ICRF heated Alcator C-Mod plasmas , 1998 .

[3] B. Braams. Radiative Divertor Modelling for ITER and TPX , 1996 .

[4] Charles F. F. Karney,et al. Approximate formula for radiofrequency current drive efficiency with magnetic trapping , 1991 .

[5] O. Naito,et al. ITER L mode confinement database , 1997 .

[6] D. N. Hill,et al. The role of neutrals in the H–L back transition of high density single-null and double-null gas-fueled discharges in DIII-D , 1998 .

[7] C. Roach,et al. High-performance discharges in the Small Tight Aspect Ratio Tokamak (START) , 1998 .

[8] Erwin Frederick Jaeger,et al. Influence of various physics phenomena on fast wave current drive in tokamaks , 1993 .

[11] J. Manickam,et al. Ideal MHD stability limits of low aspect ratio tokamak plasmas , 1997 .

[12] J. Manickam,et al. Role of the stabilizing shell in high- beta , low-q disruptions in PBX-M , 1996 .

[13] J. Manickam,et al. Characteristics of low-q disruptions in PBX , 1988 .

[14] M. Mauel,et al. Active control of 2/1 magnetic islands in a tokamak , 1998 .

[15] David Mikkelsen,et al. Current relaxation time scales in toroidal plasmas , 1989 .

[16] K. Borrass,et al. Disruptive tokamak density limit as scrape-off layer/divertor phenomenon , 1991 .

[17] Neil Pomphrey,et al. TSC simulation of Ohmic discharges in TFTR , 1993 .

[18] O. J. W. F. Kardaun,et al. Analysis of the ITER H-mode confinement database , 1993 .

[19] D. N. Hill,et al. Very high‐ and high‐confinement mode limited discharges in DIII‐D , 1996 .

[20] D. J. Hoffman,et al. THREE DIMENSIONAL MODELLING OF ICRF LAUNCHERS FOR FUSION DEVICES , 1996 .

[21] K. Lackner,et al. Tokamak Confinement in Relation to Plateau Scaling , 1990 .

[22] J. Cordey,et al. Results from the ITER H-mode threshold database , 1996 .

[23] W. M. Tang. Microinstability-based model for anomalous thermal confinement in tokamaks , 1986 .

[24] S. Jardin,et al. Dynamic modeling of transport and positional control of tokamaks , 1986 .

[25] High harmonic fast waves in high beta plasmas , 1995 .

[26] F. Hofmann,et al. Pressure and inductance effects on vertical stability of shaped tokamaks , 1993 .

[27] K. H. Burrell,et al. Flow shear induced fluctuation suppression in finite aspect ratio shaped tokamak plasma , 1995 .

[28] R. Galvão,et al. «Natural elongation» of spherical tokamaks , 1992 .