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Tuesday, May 19, 2020 | History

2 edition of Evolution of flux conserving tokamak equilibria with preprogrammed cross sections found in the catalog.

Evolution of flux conserving tokamak equilibria with preprogrammed cross sections

J. A. Holmes

Evolution of flux conserving tokamak equilibria with preprogrammed cross sections

by J. A. Holmes

  • 74 Want to read
  • 20 Currently reading

Published by [Dept. of Energy, Office of Energy Technology], Oak Ridge National Laboratory, for sale by the Natonal Technical Information Service in Oak Ridge, Tenn, Springfield, Va .
Written in English

    Subjects:
  • Tokamaks.,
  • Equilibrium.,
  • Magnetohydrodynamics.

  • Edition Notes

    StatementJ. A. Holmes, Y-K. M. Peng, S. J. Lynch ; prepared by the Oak Ridge National Laboratory.
    SeriesORNL/TM ; 6761, ORNL/TM -- 6761.
    ContributionsPeng, Y-K. M., Lynch, S. J., Oak Ridge National Laboratory.
    The Physical Object
    Paginationv, 43 p. :
    Number of Pages43
    ID Numbers
    Open LibraryOL17648962M

    The well-established topics of fusion plasma physics -- basic plasma phenomena, Coulomb scattering, drifts of charged particles in magnetic and electric fields, plasma confinement by magnetic fields, kinetic and fluid collective plasma theories, plasma equilibria and flux surface geometry, plasma waves and instabilities, classical and You can write a book review and share your experiences. Other readers will always be interested in your opinion of the books you've read. Whether you've loved the book or not, if you give your honest and detailed thoughts then people will find new books that are right for ://

    We present initial results in the development of a gyrokinetic particle-in-cell code for the whole-volume modeling of stellarators. This is achieved through two modifications to the X-point Gyrokinetic Code (XGC), originally developed for tokamaks. One is an extension to three-dimensional geometries with an interface to Variational Moments Equilibrium Code (VMEC) :// It is noted that, as in the circular cross-section tokamak, the neoclassical ion heat flux decreased at some range of the parameter a and the collisional parameter b = 3M i q 2 R 2 /(2T i). It is also confirmed that for these configurations the formula for the ion poloidal velocity U q i = kU Ti is the same as the one for a circular ?script=sci_arttext&pid=S

    This approach provides effective methods and insights for the interpretation of plasma phenomena on virtually all scales, ranging from the laboratory to the universe. The text will be of value to senior-level undergraduates and graduate students in physics, astrophysics and :// Nuclear Reactors, Nuclear Fusion and Fusion Engineering Aasen A., Olsson P. (Eds) Nova Science Publishers, New York, , pages, ISBN: Two of the papers in this collection review modeling approaches to turbulent mixing and void drift in sub-channel analysis and the history of magnetic confinement fusion power plant conceptual


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Evolution of flux conserving tokamak equilibria with preprogrammed cross sections by J. A. Holmes Download PDF EPUB FB2

JOURNAL OF COMPUTATIONAL PHYS () Evolution of Flux-Conserving Tokamak Equilibria with Preprogrammed Cross Sections* J. HOLMES Computer Sciences Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee Y.-K.

PENG Fusion Energy Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee AND S. LYNCH Computer Sciences Division, Evolution of flux-conserving tokamak equilibria with preprogrammed cross sections: Authors: Holmes, J.

A.; Peng, Y.-K. it is possible to prescribe the evolution of the plasma boundary to permit the treatment of cases in which the plasma cross section changes significantly and in which precise plasma positioning and shaping are required 35H.

Evolution of Flux-conserving Tokamak Plasmas with Preprogrammed Cross Sections. The location and evolution of the plasma cross section boundary are precisely specified through the use of a fixed boundary equilibrium technique.

In moving boundary studies (e.g., plasma compression) the resulting system of equations is advanced in time from an The location an evolution of the plasma cross section boundary are precisely specified through the use of a fixed boundary equilibrium technique.

In moving boundary studies (e.g., plasma compression) the resulting system of equations is advanced in time from an inital more» state by a procedure which utilizes two nested predictor-corrector Translated from Chislennye Metody Resheniya Obratnykh Zadach Matematicheskoi Fiziki, pp.

–, The evolution of MHD equilibria toward high is modeled by magnetic flux conservation with a given q() and by single fluid particle and energy balances which determine p(, t). This book bridges the gap between general plasma physics lectures and the real world problems in MHD stability.

In order to support the understanding of concepts and their implication, it refers to real world problems such as toroidal mode coupling or nonlinear evolution in a conceptual and phenomenological approach. Detailed mathematical treatment will involve classical linear stability  › Home › Subjects › Physics & Astronomy › Plasma Physics.

A transport model for describing electron and ion plasmatemperatures is developed on the basis of the canonical profile theory for a tokamak with an arbitrary cross :// Simulation technique of free-boundary equilibrium evolution in plasma ramp-up phase Article in Computer Physics Communications (9) September with 17 Reads How we measure 'reads' On the other hand, the choice of ¥() ing high beta equilibria.

is a critical factor in obtain In flux conserving dynamics, In this section, the FCT model provides the requisite (but implicit) means for finding F. the safety factor profile q(ty) = FVf/4ïï2 is fixed because the magnetic fluxes move with the plasma [1]. JOURNAL OF COMPUTATIONAL PHYS () Dynamic Modeling of Transport and Positional Control of Tokamaks S.

JARDIN, N. POMPHREY, AND J. DELUCIA Plasma Physics Laboratory, Princeton University, Princeton, New Jersey Received Aug ; revised December 5, DEDICATED TO THE MEMORY OF RAYMOND C. GRIMM We describe a @article{osti_, title = {Sawtooth oscillation in tokamaks}, author = {Park, W and Monticello, D A}, abstractNote = {A three-dimensional nonlinear toroidal full MHD code, MH3D, has been used to study sawtooth oscillations in tokamaks.

The profile evolution during the sawtooth crash phase compares well with experiment, but only if neoclassical resistivity is used in the rise ://   “Finite beta effects on the troidal field ripple in three dimensional tokamak equilibria”, Yasuhiro Suzuki, Yuji Nakamura, and Katsumi Kondo Nuclear Fusion, Vol () 3-D MHD equilibrium calculation with free-boundary constraint by the VMEC number of   Web view.

Theoretical [1] and experimental [2–3] results show that a stabilized pinch in a flux conserving shell tends to generate a is found even for moderate equilibrium displacements.

In the belt geometry, equilibria with highly elongated plasma cross-section are possible, also at high compression ratios. Pulsed High Beta Plasmas contains The evolution of the flux-surface averaged electron density n e (ρ, t) resulting from radial transport and a net source is modeled as a PDE on the domain Ω = {(t, ρ) ∈ ℝ ∣ t 0 ≤ t ≤ t f, 0 ≤ ρ ≤ ρ e}, where the constant ρ e > 1 represents the location of the scrape-off layer edge and t   @article{osti_, title = {Imaging motional Stark effect measurements at ASDEX Upgrade}, author = {Ford, O.

and Burckhart, A. and McDermott, R. and Pütterich, T. and Wolf, R. C.}, abstractNote = {This paper presents an overview of results from the Imaging Motional Stark Effect (IMSE) diagnostic obtained during its first measurement campaign at ASDEX Upgrade since installation as a Turbulence in the edge plasma of a tokamak is a key actor in the determination of the confinement properties.

The divertor configuration seems to be beneficial for confinement, suggesting an effect on turbulence of the particular magnetic geometry introduced by the X-point. Simulations with the 3D fluid turbulence code TOKAM3X are performed here to evaluate the impact of a diverted Equilibrium and stability of tokamaks Equilibrium and stability of tokamaks Kerner, Wolfgang WOLFGANG KERNER Plasmaphysik, Euratom Association, Garching bei Miinchen, F.R.G.

SUMMARY Axisymmetric, ideal MHD configurations with steady flow are computed by the finite-element method. Rectangular elements with four to nine nodes are Journal Article: Investigation of magnetic reconnection during a sawtooth crash in a high-temperature tokamak plasma   @article{osti_, title = {Sensitivity of magnetic field-line pitch angle measurements to sawtooth events in tokamaks}, author = {Ko, J., E-mail: [email protected]}, abstractNote = {The sensitivity of the pitch angle profiles measured by the motional Stark effect (MSE) diagnostic to the evolution of the safety factor, q, profiles during the tokamak sawtooth events has been investigated.

Spherical tokamak is a kind of tokamak with a very low aspect ratio (A = major radius/minor radius cross section is naturally elongated ://Experimentally the self-organization of tokamak plasmas has been demonstrated inwhen it turned out that the profile of the total plasma pressure p(ρ)/p(ρ 0) normalized to the pressure at a selected radius ρ 0 (with ρ = r/(IR/B) 1/2 the normalized plasma radius) should be the same for all tokamaks (at that time with circular cross The success of magnetically controlled thermonuclear fusion relies, among other things, on the confinement of α-particles that are not only essential for sustaining fusion conditions, but whose unanticipated losses could compromise the efficiency and, more importantly, put at risk the plasma-facing confinement of α-particles is a complex subject involving the equilibrium