Author: Masayuki Ono
Publisher:
ISBN:
Category :
Languages : en
Pages : 12
Book Description
National Spherical Torus Experiment (NSTX).
The National Spherical Torus Experiment (NSTX) Research Program and Progress Towards High Beta, Long PulseOperating Scenarios
Author: E. J. Synakowski
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 12
Book Description
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 12
Book Description
Engineering Overview of the National Spherical Torus Experiment (NSTX).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The National Spherical Torus Experiment (NSTX) Project will provide a national facility for the study of plasma confinement, heating, and current drive in a low-aspect-ratio, spherical torus (ST) configuration. The ST configuration is an alternate confinement concept which is characterized by high beta, high elongation, high bootstrap fraction, and low toroidal magnetic field compared to conventional tokamaks. The NSTX is the next-step ST experiment following smaller experiments such as the Princeton Plasma Physics Laboratory CDX-U (Current Drive Experiment-Upgrade), the START (Small Tight Aspect Ratio Tokamak) at Culham Laboratory, UK, and the HIT (Helicity Injected Tokamak) at the University of Washington, and it is smaller in scale to the MAST (Meg-Amp Spherical Tokamak) machine now under construction at Culham. This paper provides a description of the NSTX mission and gives an overview of the main engineering features of the design of the machine and facility and discusses some of the key design solutions.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The National Spherical Torus Experiment (NSTX) Project will provide a national facility for the study of plasma confinement, heating, and current drive in a low-aspect-ratio, spherical torus (ST) configuration. The ST configuration is an alternate confinement concept which is characterized by high beta, high elongation, high bootstrap fraction, and low toroidal magnetic field compared to conventional tokamaks. The NSTX is the next-step ST experiment following smaller experiments such as the Princeton Plasma Physics Laboratory CDX-U (Current Drive Experiment-Upgrade), the START (Small Tight Aspect Ratio Tokamak) at Culham Laboratory, UK, and the HIT (Helicity Injected Tokamak) at the University of Washington, and it is smaller in scale to the MAST (Meg-Amp Spherical Tokamak) machine now under construction at Culham. This paper provides a description of the NSTX mission and gives an overview of the main engineering features of the design of the machine and facility and discusses some of the key design solutions.
National Spherical Torus Experiment (NSTX).
National Spherical Torus Experiment (NSTX) Torus Design, Fabrication and Assembly
Author: James H. Chrzanowski
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 4
Book Description
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 4
Book Description
Recent Progress on the National Spherical Torus Experiment (NSTX).
National Spherical Torus Experiment (NSTX) Engineering Overview and Research Results 1999-2000
Author: C. Neumeyer
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 6
Book Description
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 6
Book Description
National Spherical Torus Experiment (NSTX) and Planned Research
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
The U.S. fusion energy sciences program began in 1996 to increase emphasis on confinement concept innovation. The NSTX [1,2] is being built at PPPL as a national fusion science research facility in response to this emphasis. NSTX is to test fusion science principles of the Spherical Torus (ST) plasmas, which include: (1) High plasma pressure in low magnetic field for high fusion power density, (2) Good energy confinement is a small-size plasma, (3) Nearly fully self-driven (bootstrap) plasma current, (4) Dispersed heat and particle fluxes, and (5) Plasma startup without complicated inboard solenoid magnet. These properties of the ST plasma, if verified, would lead to possible future fusion devices of high fusion performance, small size, feasible power handling, and improved economy. The design of NSTX is depicted in Fig. 1. The device is designed to study plasmas with major radius up to 85 cm, minor radius up to 68 cm, elongation up to 2, with flexibility in forming double-null, single-null, and inboard limited plasmas. The nominal operation calls for a toroidal field of 0.3 T for 5 s at the major radius, and a plasma current at 1 MA with q (approximately) 10 at edge. It features a compact center stack containing the inner legs of the toroidal field coils, a full size solenoid capable of delivering 0.6 Wb induction, inboard vacuum vessel, and composite carbon tiles. The center stack can be replaced without disturbing the main device, diagnostics, and auxiliary systems. The vessel will be covered fully with graphite tiles and can be baked to 350 C. Other wall conditioning techniques are also planned.
Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
The U.S. fusion energy sciences program began in 1996 to increase emphasis on confinement concept innovation. The NSTX [1,2] is being built at PPPL as a national fusion science research facility in response to this emphasis. NSTX is to test fusion science principles of the Spherical Torus (ST) plasmas, which include: (1) High plasma pressure in low magnetic field for high fusion power density, (2) Good energy confinement is a small-size plasma, (3) Nearly fully self-driven (bootstrap) plasma current, (4) Dispersed heat and particle fluxes, and (5) Plasma startup without complicated inboard solenoid magnet. These properties of the ST plasma, if verified, would lead to possible future fusion devices of high fusion performance, small size, feasible power handling, and improved economy. The design of NSTX is depicted in Fig. 1. The device is designed to study plasmas with major radius up to 85 cm, minor radius up to 68 cm, elongation up to 2, with flexibility in forming double-null, single-null, and inboard limited plasmas. The nominal operation calls for a toroidal field of 0.3 T for 5 s at the major radius, and a plasma current at 1 MA with q (approximately) 10 at edge. It features a compact center stack containing the inner legs of the toroidal field coils, a full size solenoid capable of delivering 0.6 Wb induction, inboard vacuum vessel, and composite carbon tiles. The center stack can be replaced without disturbing the main device, diagnostics, and auxiliary systems. The vessel will be covered fully with graphite tiles and can be baked to 350 C. Other wall conditioning techniques are also planned.
EBW-Bootstrap Current Synergy in the National Spherical Torus Experiment (NSTX).
Author: R. W. Harvey
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project).
Languages : en
Pages : 42
Book Description
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project).
Languages : en
Pages : 42
Book Description