Simulation of Transport in Tokamaks

Bateman, G.

doi:10.1007/978-1-4612-3092-2_14

Cited by 3 publications

(4 citation statements)

References 44 publications

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“…An alternative estimate of the cylindrical safety factor, often referred to as the engineering safety factor, is given by (9) -…”

Section: Shape Dependent Quantitiesmentioning

confidence: 99%

“…Over the last several years, simole global performance calculations [1][2][3][4][5][6][7][8][9] b.e_e been used to aid in the design of future tokamak fusion reactors. Given information about the parameters of the device, and some assumptions about the plasma (e.g., plasma shape, radial density and temperature profiles, quality of energy confinement, plasma composition), these codes can determine the fusion yield.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

ASPECT: An advanced specified-profile evaluation code for tokamaks

Stotler¹,

Reiersen²,

Bateman³

1993

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•A specified-profile, global analysis code has been developed to evaluate the performance of fusion reactor designs. Both steady-state and time-dependent calculations are carried out; the results of the former can be used in defining the parameters of the latter, if desired. In the steady-state analysis, the performance is computed at a density and temperature chosen to be consistent with input limits (e.g., density and beta) of several varieties. The calculation can be made at either the intersection of the two limits or at the point of optimum performance as the density and temperature are varied along the limiting boundaries. Two measures of performance are available for this purpose: the ignition margin or the confinement level required to achieve a prescrib.ed ignition margin. The time-dependent calculation can be configured to yield either the evolution of plasma energy as a function of time or, via an iteration scheme, the amount of auxiliary power required to achieve a desired final plasma energy. Number of bits in a word: 64Number of processors used: 1 Peripheral used: disk Number of lines in distributed program: 7923Keywords: thermonuclear fusion, tokamak reactor, specified-profile transport Nature of physical problemThe purpose of this code is to provide a quick, if largely empirical, assessment of the performance of a tokamak fusion reactor [1,2]. ASPECT first performs a steady-state analysis at a point irl the density -temperature operating space determined according to a set of user-specified criteria. The code then carries out a time-dependent calculation which can be used to address, for example, auxiliary heating requirements and helium ash buildup. Method of solutionFor the steady-state portion of the calculation, the individual terms in the global power balance equation are estimated using user-specified radial plasmaprofiles. An expression for the energy confinement time is required; a number of popular forms are included in the code. The power balance equation is solved using a Brent algorithm subroutine [3]. The reactor performance is quantified using either the ignition margin parameter or the level of confinement required to achieve a specified ignition margin.For the time-.dependent calculation, the tempor__l variation of the device parameters, the relative plasma density, and the relative auxiliary power must be input. A feedback procedure for limiting the total heating power in the plasma is available. Helium ash accumulation can be included with an adjustable global confinement time. The time-dependent global plasma evolution equations are integrated using Hindmarsh's LSODE algorithm [4]; this yields the plasma energy as a function of time. The integration can be iterated (via the Brent algorithm subroutine [3]) to determine the level of auxiliary input power required to reach a specific plasma energy at a certain time.Restrictions on the complexity of the problem Although ASPECT is designed for use with tokamak reactors, it should be • applicable to any toroidal reactor dev...

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“…An alternative estimate of the cylindrical safety factor, often referred to as the engineering safety factor, is given by (9) -…”

Section: Shape Dependent Quantitiesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

ASPECT: An advanced specified-profile evaluation code for tokamaks

Stotler¹,

Reiersen²,

Bateman³

1993

View full text Add to dashboard Cite

show abstract

“…Over the last several years, simple global performance calculations [1][2][3][4][5][6][7][8][9] have been used to aid in the design of future tokamak fusion reactors. Given information about the parameters of the device, and some assumptions about the plasma (e.g., plasma shape, radial density and temperature profiles, quality of energy confinement, plasma composition), these codes can determine the fusion yield.…”

Section: Introductionmentioning

confidence: 99%

“…We describe the code as "advanced" because of the greater number of options available to the user in comparison with related codes. [1][2][3][4][5][6][7][8][9][10] This program was developed so that it could serve as a plasma performance subroutine within a much larger engineering systems code; we discuss here the stand-alone version of the ASPECT code.…”

Section: Introductionmentioning

confidence: 99%

ASPECT: an advanced specified-profile evaluation code for tokamaks

Stotler¹,

Reiersen²,

Bateman³

1994

Computer Physics Communications

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A specified-profile, global analysis code has been developed to evaluate the performance of fusion reactor designs. Both steady-state and time-dependent calculations are carried out; the results of the former can be used in defining the parameters of the latter, if desired. In the steady-state analysis, the performance is computed at a density and temperature chosen to be consistent with input limits (e.g., density and beta) of several varieties. The calculation can be made at either the intersection of the two limits or at the point of optimum performance as the density and temperature are varied along the limiting boundaries. Two measures of performance are available for this purpose: the ignition margin or the confinement level required to achieve a prescribed ignition margin. The time-dependent calculation can be configured to yield either the evolution of plasma energy as a function of time or, via an iteration scheme, the amount of auxiliary power required to achieve a desired final plasma energy. Operating systems: UNICOS, Sun OS Programming language used: FORTRAN Memory required: 152000 words Number of bits in a word: 64Number of processors used: 1 Peripheral used: disk Number of lines in distributed program: 7923Keywords: thermonuclear fusion, tokamak reactor, specified-profile transport Nature of physical problemThe purpose of this code is to provide a quick, if largely empirical, assessment of the performance of a tokamak fusion reactor [1,2]. ASPECT first performs a steady-state analysis at a point in the density -temperature operating space determined according to a set of user-specified criteria. The code then carries out a time-dependent calculation which can be used to address, for example, auxiliary heating requirements and helium ash buildup. Method of solutionFor the steady-state portion of the calculation, the individual terms in the global power balance equation are estimated using user-specified radial plasma profiles. An expression for the energy confinement time is required; a number of popular 2 forms are included in the code. The power balance equation is solved using a Brent algorithm subroutine [3]. The reactor performance is quantified using either the ignition margin parameter or the level of confinement required to achieve a specified ignition margin.For the time-dependent calculation, the temporal variation of the device parameters, the relative plasma density, and the relative auxiliary power must be input. A feedback procedure for limiting the total heating power in the plasma is available. Helium ash accumulation can be included with an adjustable global confinement time. The time-dependent global plasma evolution equations are integrated using Hindmarsh's LSODE algorithm [4]; this yields the plasma energy as a function of time. The integration can be iterated (via the Brent algorithm subroutine [3]) to determine the level of auxiliary input power required to reach a specific plasma energy at a certain time. Restrictions on the complexity of the problemAlthoug...

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