Modelling of post-disruptive plasma loss in the princeton beta experiment

S. C. Jardin; J. Delucia; M. Okabayashi; N. Pomphrey; M. Reusch; S. Kaye; H. Takahashi

doi:10.1088/0029-5515/27/4/003

Modelling of post-disruptive plasma loss in the princeton beta experiment

S. C. Jardin, J. Delucia, M. Okabayashi, N. Pomphrey, M. Reusch, S. Kaye, H. Takahashi

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31 Scopus citations

Abstract

The free-boundary, axisymmetric tokamak simulation code TSC is used to model the transport time-scale evolution and positional stability of the Princeton Beta Experiment (PBX). A disruptive thermal quench will cause the plasma column to move inwards in major radius. It is shown that the plasma can then lose axisymmetric stability, causing it to displace exponentially off the midplane, terminating the discharge. The accuracy of the code is verified by modelling several controlled experimental shots in PBX.

Original language	English (US)
Pages (from-to)	569-578
Number of pages	10
Journal	Nuclear Fusion
Volume	27
Issue number	4
DOIs	https://doi.org/10.1088/0029-5515/27/4/003
State	Published - Apr 1987

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Condensed Matter Physics

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abstract = "The free-boundary, axisymmetric tokamak simulation code TSC is used to model the transport time-scale evolution and positional stability of the Princeton Beta Experiment (PBX). A disruptive thermal quench will cause the plasma column to move inwards in major radius. It is shown that the plasma can then lose axisymmetric stability, causing it to displace exponentially off the midplane, terminating the discharge. The accuracy of the code is verified by modelling several controlled experimental shots in PBX.",

author = "Jardin, \{S. C.\} and J. Delucia and M. Okabayashi and N. Pomphrey and M. Reusch and S. Kaye and H. Takahashi",

year = "1987",

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doi = "10.1088/0029-5515/27/4/003",

language = "English (US)",

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pages = "569--578",

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AU - Jardin, S. C.

AU - Delucia, J.

AU - Okabayashi, M.

AU - Pomphrey, N.

AU - Reusch, M.

AU - Kaye, S.

AU - Takahashi, H.

PY - 1987/4

Y1 - 1987/4

N2 - The free-boundary, axisymmetric tokamak simulation code TSC is used to model the transport time-scale evolution and positional stability of the Princeton Beta Experiment (PBX). A disruptive thermal quench will cause the plasma column to move inwards in major radius. It is shown that the plasma can then lose axisymmetric stability, causing it to displace exponentially off the midplane, terminating the discharge. The accuracy of the code is verified by modelling several controlled experimental shots in PBX.

AB - The free-boundary, axisymmetric tokamak simulation code TSC is used to model the transport time-scale evolution and positional stability of the Princeton Beta Experiment (PBX). A disruptive thermal quench will cause the plasma column to move inwards in major radius. It is shown that the plasma can then lose axisymmetric stability, causing it to displace exponentially off the midplane, terminating the discharge. The accuracy of the code is verified by modelling several controlled experimental shots in PBX.

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EP - 578

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 4

ER -

Modelling of post-disruptive plasma loss in the princeton beta experiment

Abstract

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