An investigation of cyclotron instability potential and adiabatic compression of a plasma in a mirror machine

Bortnikov, A.V.; Brevnov, N. N.; Zhukovskii, V. G.; Romanovskii, M.K.

doi:10.1088/0032-1028/9/5/313

Cited by 10 publications

(18 citation statements)

References 5 publications

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“…By the mid-1970's the divertor concept, originally developed for the C-stellarator at Princeton [85,86], was being tried on a number of tokamaks, starting with DIVA in Japan [87], T-12 in the USSR [88] and DITE in the U.K. [89]. The original divertor concept was to remove the source of first plasma contact to some remote location away from the thermonuclear plasma where impurities generated by the wall contact could be retained [64].…”

Section: Insert Tablementioning

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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Section: Insert Tablementioning

confidence: 99%

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

et al. 2001

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“…The first two equations in expression (17) describe the rotation of the ion around a centre which does not coincide with the origin of the co-ordinates, and R is the distance from the origin of the co-ordinates to the centre of rotation of the ion. In experimental installations [2,5] we generally find two cases: (1) the centre of rotation coincides with the origin of the co-ordinates, i.e. R = 0; and (2) the centre of rotation is at a distance rj from the origin of the co-ordinates, i. e. R = r t .…”

Section: Eh 2cmentioning

confidence: 99%

“…Let us consider the particular case corresponding to the conditions found in the AC device [2], where the equilibrium ion distribution function is 6, a function of the velocities:…”

Section: Exp -1m I +Arccosmentioning

confidence: 99%

“…The aim of this study is to investigate the ioncyclotron instability of oscillations in a plasma cylinder in which cold magnetized electrons perform Langmuir oscillations while the ions (with an anisotropic velocity distribution) oscillate across the magnetic field. Allowance is made for the specific properties of the ion trajectories obtained in the AC device [2]. We know from experiment [2] that the growth rate of waves travelling in the direction of the ions is far greater than that of waves travelling in the opposite direction.…”

mentioning

confidence: 99%

“…Allowance is made for the specific properties of the ion trajectories obtained in the AC device [2]. We know from experiment [2] that the growth rate of waves travelling in the direction of the ions is far greater than that of waves travelling in the opposite direction.…”

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confidence: 99%

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Cyclotron instability in a plasma cylinder

Klopovsky¹

1970

Nucl. Fusion

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The author analyses ion-cyclotron instability of oscillations in a plasma cylinder in which cold magnetized electrons perform Langmuir oscillations in the magnetic field direction while the ions (with an anisotropic velocity distribution) oscillate across the magnetic field. Dispersion equations are obtained for waves rotating in the direction of ion rotation and in the opposite direction. It is shown that the wave build-up is most intense in waves propagated in the direction of ion rotation.

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Divertor experiment in DIVA

1978

Nucl. Fusion

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An axisymmetric divertor is investigated over a wide range of plasma parameters in the DIVA tokamak. Empirical scaling for scrape-off-layer plasma parameters is obtained. In an optimum discharge, 75% of the energy loss by conduction and convection and 33% of the total particle loss are guided into the divertor. By reducing the plasma-wall interactions and shielding impurity influx from the plasma, the divertor decreases both low- and high-Z impurities. Consequently, the radiation loss is reduced by a factor of 2–4, and the energy confinement time increases by a factor of 2.5.

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An investigation of cyclotron instability potential and adiabatic compression of a plasma in a mirror machine

Cited by 10 publications

References 5 publications

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

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

Cyclotron instability in a plasma cylinder

Divertor experiment in DIVA

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