Arcing studies in the dite tokamak using a time-resolved arc detector

Goodall, Dominic

doi:10.1016/0022-3115(80)90315-3

Cited by 31 publications

(10 citation statements)

References 10 publications

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“…The passive plate poloidal gaps [e.g., Fig.4(b)] exhibited a voltage difference on the order of several hundred volts which may to be related in part to run away electron effects and plasma motion as was also seen on the outer poloidal limiter [e.g., Fig.4(c)]. The voltages on the outer poloidal limiter at breakdown were similar to those measured on other tokamak limiters at breakdown (100-800 V) and have been related in part to runaway electrons, arcing, and plasma motion [5][6][7][8]. Figure 5 shows the behavior of the same waveforms at disruption.…”

Section: Methodssupporting

confidence: 66%

Diagnostic method for measuring plasma-induced voltages on the PBX-M (Princeton Beta Experiment-Modified) stabilizing shell

Kugel¹,

Okabayashi²,

Schweitzer³

1990

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The Princeton Beta Experiment-Modified (PBX-M) has a close-fitting, conducting, passive plate, stabilizing shell which nearly surrounds highly indented, bean-shaped plasmas. The proximity of this electrically isolated shell to a large fraction of the plasma surface allows measurements similar to previous work on other tokamaks using floating probes and limiters. Measurements were performed to characterize the plasma-induced voltages on the PBX-M passive plate stabilizing shell during high-p" plasmas. Voltage differences were measured between the respective passive plate toroidal and poloidal gaps, the respective passive plates and the vessel, and an outer poloidal graphite limiter and its passive plate. The calibration and qualification testing procedures are discussed. The initial measurements found that the largest voltages were observed at plasma start-up and at the plasma current disruption and exhibited characteristics depending on operating conditions. The highest voltages observed have been at disruption and were less than 2 kV DISCLAIMER This report was prepared as a» account of worlr sponsored by an agency of (he United Stales Government.

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Section: Methodssupporting

confidence: 66%

Diagnostic method for measuring plasma-induced voltages on the PBX-M (Princeton Beta Experiment-Modified) stabilizing shell

Kugel¹,

Okabayashi²,

Schweitzer³

1990

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“…(a [475], b [476], c [496], d [480], e [497], f [498], g [499], h [500], i [501], j [502], k [503], l [504], m [505], n [506], o [353], p [507], q [508], r [509], s [510], t [511], u [109], v [492], w [493],…”

Section: Insert Table 10mentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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“…Therefore the assumption may be justified that our probe measures practically the whole arc current. The function of this probe is similar to that ofthe probe used in DIT€ (Goodall 1980). In contrast to the arrangement in DITE.…”

Section: The Arc Currentmentioning

confidence: 91%

Simulation experiments on unipolar arcs

Stampa¹,

Kruger²

1983

J. Phys. D: Appl. Phys.

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A plasma source is described which produces a plasma beam with a density ne=1013 cm-3 and a temperature of 5-25 eV, 50 cm outside the actual discharge. In this plasma unipolar arcs are ignited without applying an external voltage. It is shown that by plasma cleaning of the surface this type of arcing can be completely suppressed for the above stated parameters. A microcontamination deliberately attached to a wall probe of stainless steel enables one to predetermine the ignition point of a unipolar arc, and gives the possibility of measuring the arc current. The erosion phenomena of single arc events are compared with those from bipolar arcs and wall probes in tokamaks.

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Arcing studies in the dite tokamak using a time-resolved arc detector

Cited by 31 publications

References 10 publications

Diagnostic method for measuring plasma-induced voltages on the PBX-M (Princeton Beta Experiment-Modified) stabilizing shell

Diagnostic method for measuring plasma-induced voltages on the PBX-M (Princeton Beta Experiment-Modified) stabilizing shell

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Simulation experiments on unipolar arcs

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