Aspect Ratio Scaling of Ideal No-wall Stability Limits in High Bootstrap Fraction Tokamak Plasmas PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Aspect Ratio Scaling of Ideal No-wall Stability Limits in High Bootstrap Fraction Tokamak Plasmas PDF full book. Access full book title Aspect Ratio Scaling of Ideal No-wall Stability Limits in High Bootstrap Fraction Tokamak Plasmas by Jonathan Edward Menard. Download full books in PDF and EPUB format.
Author: Jonathan Edward Menard
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 0
Get Book Here
Book Description
Author: Jonathan Edward Menard
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project)
Languages : en
Pages : 0
Get Book Here
Book Description
Author: Jonathan Edward Menard
Publisher:
ISBN:
Category : National Spherical Torus Experiment (Project).
Languages : en
Pages : 8
Get Book Here
Book Description
Author: Jonathan Edward Menard
Publisher:
ISBN:
Category : Plasma density
Languages : en
Pages : 4
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Low aspect ratio tokamaks can potentially provide a high ratio of plasma pressure to magnetic pressure[beta] and high plasma current I at a modest size, ultimately leading to a high power density compact fusion power plant. For the concept to be economically feasible, bootstrap current must be a major component of the plasma current. A high value of the Troyon factor[beta][sub N] and strong shaping are required to allow simultaneous operation at high[beta] and high bootstrap current fraction. Ideal magnetohydrodynamic stability of a range of equilibria at aspect ratio 1.4 is systematically explored by varying the pressure profile and shape. The pressure and current profiles are constrained in such a way as to assure complete bootstrap current alignment. Both[beta][sub N] and[beta] are defined in terms of the vacuum toroidal field. Equilibria with[beta][sub N][ge] 8 and[beta] - 35% to 55% exist which are stable to n=[infinity] ballooning modes, and stable to n= 0, 1,2,3 kink modes with a conducting wall. The dependence of[beta] and[beta][sub N] with respect to aspect ratio is also considered.
Author:
Publisher:
ISBN:
Category : Electronic journals
Languages : en
Pages : 948
Get Book Here
Book Description
Author: Stefano Bernabei
Publisher: Compositori
ISBN:
Category : Science
Languages : en
Pages : 436
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Browse> Conferences> Fusion Engineering, 1989. Pro Back to Results MHD equilibrium and stability considerations for high-aspect-ratio ARIES-I tokamak reactors .102446 searchabstract .Peng, Y.-K.M. ; Strickler, D.J. ; Hogan, J.T. ; Whitson, J.C. ; Bathke, C.G. ; Evans, K., Jr. ; Jardin, S.C. ; Klasky, M. ; Leuer, J.A. ; Oak Ridge Nat. Lab., TN This paper appears in: Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on Issue Date : 2-6 Oct 1989 On page(s): 1278 - 1282 vol. 2 Meeting Date : 02 Oct 1989-06 Oct 1989 INSPEC Accession Number: 3809362 Digital Object Identifier : 10.1109/FUSION. 1989.102446 Date of Current Version : 06 August 2002 Abstract The requirements of (1) an external poloidal-field coil (PFC) system with minimum stored energy, (2) double-null divertor plasmas with elongated D shape, (3) adequate passive stabilization of plasma vertical displacement by a vacuum vessel located behind the blanket zone, and (4) an enhanced plasma beta limit in the first stability regime are incorporated in the Advanced Reactor Innovation and Evaluation Study-I (ARIES-I) concept for a high-field tokamak reactor with high aspect ratio (A=4.5). The plasma current and pressure profiles are also made consistent with enhanced bootstrap current and reduced current drive power by means of ion cyclotron wave or neutral beam injection. These lead to plasmas characterized by an elongation of 1.8 to the divertor X-point, a triangularity of 0.7, a safety factor of ~1.5, a safety factor at the edge>4, a plasma beta of ~2%, and a poloidal beta of ~0.5. With a plasma current of 11 MA, a toroidal field of 13 T at the major radius of 6.5 m, and over 3.5 m of clearance between the PFCs and the plasma edge, the stored energy in the PFC system ranges from 20 GJ during plasma operation at low beta, to 12 GJ during plasma operation at high beta.
Author: Andrey Martynov
Publisher:
ISBN:
Category :
Languages : en
Pages : 101
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
One promising approach to maintaining stability of high beta tokamak plasmas is the use of a conducting wall near the plasma to stabilize low-n ideal MHD instabilities. However, with a resistive wall, either plasma rotation or active feedback control is required to stabilize the more slowly growing resistive wall modes (RWMs). Experiments in the DIII-D, PBHX-M, and HBT-EP tokamaks have demonstrated that plasmas with a nearby conducting wall can remain stable to the n= 1 ideal external kink above the beta limit predicted with the wall at infinity, with durations in DIII-D up to 30 times[tau][sub w], the resistive wall time constant. More recently, detailed, reproducible observation of the n= 1 RWM has been possible in DIII-D plasmas above the no-wall beta limit. The DIII-D measurements confirm characteristics common to several RWM theories. The mode is destabilized as the plasma rotation at the q= 3 surface decreases below a critical frequency of 1 to 7 kHz. The measured mode growth times of 2 to 8 ms agree with measurements and numerical calculations of the dominant DIII-D vessel eigenmode time constants, [tau][sub w]. From its onset, the RWM has little or no toroidal rotation and rapidly reduces the plasma rotation to zero. Both DIII-D and HBT-EP have adopted the smart shell concept as an initial approach to control of these slowly growing RWMs; external coils are controlled by a feedback loop designed to make the resistive wall appear perfectly conducting by maintaining a net zero radial field at the wall. Initial experiment results from DIII-D have yielded encouraging results.
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 404
Get Book Here
Book Description
