F. V. Chernyshev

Injection of a High-Density Plasma into the Globus-M Spherical Tokamak

A new type of plasma source with titanium hydride granules used as a hydrogen accumulator was employed to inject a dense, highly ionized plasma jet into the Globus-M spherical tokamak. The experiments have shown that the jet penetrates through the tokamak magnetic field and increases the plasma density, without disturbing the stability of the plasma column. It is found that, when the plasma jet is injected before a discharge, more favorable conditions (as compared to those during gas puffing) are created for the current ramp-up at a lower MHD activity in the plasma column. Plasma injection at the instant of maximum current results in a more rapid growth in the plasma density in comparison to gas puffing.

The influence of plasma horizontal position on the neutron rate and flux of neutral atoms in injection heating experiment on the TUMAN-3M tokamak

Horizontal displacement of plasma along the major radius has been found to significantly influence the fluxes of 2.45 MeV DD neutrons and high-energy charge-exchange atoms from neutral beam injection (NBI) heated plasma of the TUMAN-3M tokamak. An inward shift by ΔR = 1 cm causes 1.2-fold increase in the neutron flux and 1.9-fold increase in the charge-exchange atom flux. The observed increase in the neutron flux is attributed to joint action of several factors-in particular, improved high-energy ion capture and confinement and, probably, decreased impurity inflow from the walls, which leads to an increase in the density of target ions. A considerable increase in the flux of charge-exchange neutrals in inward-shifted plasma is due to the increased number of captured high-energy ions and, to some extent, the increased density of the neutral target. As a result of the increase in the content of high-energy ions, the central ion temperature Ti(0) increased from 250 to 350 eV. The dependence of the neutron rate on major radius R0 should be taken into account when designing compact tokamak-based neutron sources.

Background and radiation resistance tests of neutral particle analyzer detectors for ITER by using a fast neutron beam

The radiation resistance and background sensitivity of scintillation (Hamamatsu H8500D photo-multiplier) and semiconductor (ORTEC BF-018-100-60 and BU-012-050-100) detectors to neutron and gamma radiation were investigated. Conclusions are drawn concerning the possibility of using such detectors in neutral particle analyzers that are being developed for ITER at the Ioffe Institute.

Particle diagnostics of ion cyclotron resonance plasma heating in the Globus-M tokamak

Basic experimental results on cyclotron heating of the ion plasma component in the Globus-M spherical tokamak obtained by means of the ACORD-12 charge-exchange ion analyzer are presented. A procedure for determining the maximum energy of fast ions confined in the plasma is described. The procedure was applied to estimate the limiting energy of hydrogen minority ions accelerated during ion cyclotron heating in the Globus-M tokamak. The experimental evaluation of the maximum hydrogen ion energy is confirmed by simulations of ion orbits. Recommendations for optimizing experiments on ion cyclotron heating in the Globus-M tokamak are formulated.

The first experimental HF heating of plasma at ion cyclotron frequencies in the globus-M spherical tokamak

We present the results of the first experiments on the HF heating of hydrogen-deuterium plasma at ion cyclotron frequencies in the Globus-M spherical tokamak. A power of 200 kW at a frequency of 9.1 MHz introduced via a single-loop antenna led to an increase in the ion temperature from 170 to 300 eV. Characteristic times of the ion temperature buildup and decay corresponded to the ion energy confinement time in the tokamak plasma.

A method for monitoring the parameters of a stripping target in neutral particle analyzers for the ITER

A method is described, which will be used as a basis for designing a system for monitoring the parameters of a stripping target in neutral particle analyzers being developed for neutral particle diagnostics of the ITER plasma. This method is based on examining the target by a beam of alkali ions and measuring the energy spectrum of the beam passed through it. Results of testing of this method at the experimental facility—a model of the monitoring system—are presented. Based on analysis of the experimental data obtained in the study, conclusions are drawn on the applicability of this method to monitoring of the stripping target parameters.

On the role of graphite chamber-wall lining in experiments on the ion-cyclotron resonance plasma heating in the globus-M spherical tokamak

Comparative results of experiments on the ion-cyclotron resonance (ICR) heating of plasma in the Globus-M spherical tokamak using a hydrogen-deuterium mixture are presented. The experimental data are analyzed over a long period of time during which the internal surface of the chamber walls was gradually coated with graphite plates. The observed monotonic decrease in the efficiency of ICR plasma heating in the chamber with increasing graphite coverage can be explained by a growth in the high-frequency power absorption in the coating material. Results of numerical simulation of this process are reported.

Study of plasma heating in discharges with neutral beam injection in the Globus-M spherical tokamak

Results from experimental studies on the injection of high-energy neutral hydrogen beams into the plasma of the Globus-M spherical tokamak are reviewed. In the Introduction, the importance of these studies for implementing the controlled fusion research program and constructing the ITER tokamak is proved. Some problems related to the use of neutral beam injection in small and low-aspect-ratio tokamaks is analyzed. Results are presented from numerical simulations of the experiment by using the ASTRA transport code. It is shown that the use of neutral beam injection in the Globus-M tokamak ensures efficient ion heating and increases the plasma stored energy. The greater part of the review is devoted to the survey of experiments on the injection of 22-to 30-keV hydrogen and deuterium beams with a power of 0.4–0.8 MW into the plasma of the Globus-M spherical tokamak in a wide range of plasma currents and densities. The experimental results are analyzed and compared with the results of numerical simulations. The achievement of top plasma parameters is highlighted.

The angular distribution of light ions past a thin carbon foil

The scattering angles of ions formed upon the transmission of a monoenergetic beam of hydrogen (5–230 keV), deuterium (5–25 keV), or helium-4 (52–230 keV) atoms through a thin (2.7 μg/cm2) carbon foil were measured. The experimental data are compared to the results of calculations using an SRIM-2000 numerical modeling program. For hydrogen, the isotope effect (i.e., dependence of the angular distribution on the isotope mass) is estimated.

Effect of the mass resolution of a multichannel atomic analyzer on the measured isotopic composition of hydrogen plasma

The isotopic composition of the ionic component of a plasma can be determined by analyzing streams of charge-transfer atoms registered by atomic particle analyzers as they leave the plasma. Since the mass resolution of an atomic analyzer is finite, difficulties often arise in the determinations of the concentration of a small impurity against the background of the main constituent of the plasma. This paper presents a method that can be used to estimate the size of the background signal and to introduce the necessary corrections when such measurements are carried out.