Magnetohydrodynamic equilibria and local stability of axisymmetric tokamak plasmas

Peng, Yueng Kay Martin; Dory, R.A.; Nelson, Daniel B.; Sayer, R. O.

doi:10.1063/1.862246

Cited by 13 publications

(9 citation statements)

References 20 publications

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“…We describe a modifica tion in which the safety factor q( v i < ) , a function that is readily inferred from experimental measurements and used in most reactor design considerations, is prescribed. Further, it is the appro priate quantity to specify when computing a series of equilibria from flux conserving principles [5].…”

Section: Solution Procedures With P(y) and Q(t) Specifiedmentioning

confidence: 99%

“…(14) and 15 as studies of global modes with the PEST code [21] indicates that this equilibrium should be stable with respect to ideal MHD modes . The numerical results with flux conserving constraints [5] are shown in Pigs. 7 and 8.…”

Section: A the Princeton Large Torus (Plt)mentioning

confidence: 99%

“…Interest [3,4] in tokamaks with noncircular cross sec tions makes these calculations even more essential. Detailed parametric studies of high-B tokamak properties [5] may deter mine the criteria for design of the next generation of tokamak devices. Equilibrium calculations play a major role in reactor studies where a knowledge of the plasma configuration (produced, for example, by divertors) provides the basic framework for detailed system design.…”

Section: Introductionmentioning

confidence: 99%

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Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibria

Johnson

Dalhed

Greene

et al. 1979

Journal of Computational Physics

125

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Section: Solution Procedures With P(y) and Q(t) Specifiedmentioning

confidence: 99%

Section: A the Princeton Large Torus (Plt)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibria

Johnson

Dalhed

Greene

et al. 1979

Journal of Computational Physics

125

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“…3.2-3, the liquid lithium system yields a slightly higher BHP up to ^ 1 yr after shutdown than those for the helium-or water-cooled solid breeder systems. Such a high BHP in the liquid lithium system stems from the fact that the hard neutron spectrum inherent in the lithium blanket (Table 3. [2][3][4][5][6][7][8][9][10][11][12][13][14]. First wall temperatures of 300 and 500°C were assumed for the calculation.…”

Section: Neutron Multipliermentioning

confidence: 99%

STARFIRE: a commercial tokamak reactor

Baker¹,

Abdou²,

DeFreece³

et al. 1979

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STARFIRE project organization 2 2.1-1 Major radius as a function of neutron wall load at four values of the aspect ratio, A 2.1-2 Cost of energy as a function of neutron wall load .... 2.1-3 B as a function of A at several values of F ..... in nw 2.1-4 Variation of the maximum magnetic field with the o-particle concentration, n /n DT , and other impurity concentration, n Be /n DT. .. . ? 2.1-5 Variation of the maximum magnetic field and plasma current with the average electron temperature, Te 2.1-6 Cost of energy as a function of aspect ratio for a steadystate reactor in two cases for the electrical power, P r f, required for the current-drive system: P r f = 0 and P r £ = 502-84A where A is the aspect ratio 2.2-1 STARFIRE reference design 2.2-2 STARFIRE reactor design 2.2-3 Shield design 31 3.1-1 Maximum stable beta versus q J • 36 3.1-2 Limiter/vacuum duct concept 46 3.2-1 Effect of structural materials on biological hazard potential 79 3.2-2 Isotopic contribution to BHP in air for Li blanket system with ferritic steel type X as the structural material 80 3.2-3 Effect of coolant materials 82 3.2-4 Predicted tritium inventory in candidate solid breeding materials (20 mesh) as a function of temperature after low-fluence irradiations 88 3.2-5 Pressurized module concept 94 3.2-6 Blanket module cross section-helium cooled 100 3.2-7 A schematic for the water-cooled blanket design 103 3.2-8 Backup: Lithium-cooled blanket 105 vii List of Figures (Continued) Page 3.3-1 A schematic of the heat transport and power cycle .... 107 3.3-2 Effect of pipe size and number of primary helium loops on pumping power for piping system only (steam generator and blanket pumping power not included) Ill 3.4-1 STARFIRE: TF-Coils. (24 kA conductor; 7-9 Tesla region) 122 3.4-2 STARFIRE: TF-Coils. [24 kA conductor; low field region (0-5 Tesla)] 3.4-3 STARFIRE: TF-Coils. (Conductor/support strip modules; 7-9 Tesla field region) 3.4-4 STARFIRE: TF-Coils [Conductor/support strip modules; low field region (0-5 Tesla)] 3.4-5 STARFIRE TF coil out of plane load 3.5-1 Vacuum pumping requirements for limiter-vacuum system. . 3.5-2 Fuel cycle scenario for STARFIRE 3.6-1 STARFIRE facility 3.8-1 Relative external dose from plume vs distance (STARFIRE Design) List of Tables Page 1.1-1 STARFIRE task responsibilities 3 1.1-2 STARFIRE advisory committees 4 2.2-1 STARFIRE major design features 25 2.2-2 STARFIRE plasma parameters 26 2.2-3 STARFIRE impurity control 27 2.2-4 STARFIRE plasma current drive and heating 28 2.2-5 STARFIRE major design characteristics for first-wall/ blanket 28 2.2-6 STARFIRE major design characteristics for the shield system ..

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“…Such instabilities enable a spontaneous and self-sustained motion of a solid body which can be used to convert this mechanical energy into electrical form. [1][2][3] The flapping of a flexible plate in an axial flow (thereafter referred to as a "flag") is a canonical example of such instabilities. Due to its rich and complex dynamics, this instability has been extensively studied during the last century.[4] The origin of this instability lies in a competition between the destabilizing fluid force and the stabilizing structural elasticity.…”

mentioning

confidence: 99%

Resonance-induced enhancement of the energy harvesting performance of piezoelectric flags

Xia

Michelin

Doaré

2015

Applied Physics Letters

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International audienceThe spontaneous flapping of a flag can be used to produce electrical energy from a fluid flow when coupled to a generator. In this paper, the energy harvesting performance of a flag covered by a single pair of polyvinylidene difluoride piezoelectricelectrodes is studied both experimentally and numerically. The electrodes are connected to a resistive-inductive circuit that forms a resonant circuit with the piezoelectric's intrinsic capacitance. Compared with purely resistive circuits, the resonance between the circuit and the flag's flapping motion leads to a significant increase in the harvested energy. Our experimental study also validates our fluid-solid-electric nonlinear numerical model

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Magnetohydrodynamic equilibria and local stability of axisymmetric tokamak plasmas

Abstract: NOTICE This document contains information of a preliminary nature and was praparad priri~arily for Internal use at the Oak Ridge NationalLaboratory. I t is subject t o revision or correction and therefore does not represent a final report.

Cited by 13 publications

References 20 publications

Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibria

Numerical determination of axisymmetric toroidal magnetohydrodynamic equilibria

STARFIRE: a commercial tokamak reactor

Resonance-induced enhancement of the energy harvesting performance of piezoelectric flags

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