This paper presents the results of spectroscopic measurements of plasma in a linear simulator of a plasma-beam installation (PBI) for conducting materials science research. For the first time, non-contact optical diagnostic methods were employed to measure the plasma parameters in the PBI. These measurements were allowed for the clarification of the PBI plasma parameters and the identification of transition zones in different operational modes. Analysis of the plasma emission spectrum enabled the identification of impurity spectral lines and the estimation of key plasma parameters under varying experimental conditions. The spectra were recorded using two optical spectrometers covering a wavelength range of 200–800 nm. The experimental conditions varied in terms of electron beam accelerating voltage (1–5 kV), working gas pressure (1–6 mTorr), and target bias voltage (from −500 to −100 V). The Boltzmann plot method and Stark broadening of the Balmer lines were used to estimate electron temperature and density. Based on the obtained spectroscopic data, the electron density and the electron temperature were determined. The methods described in this study are applicable to linear plasma devices.

The paper presents the results of the first measurements of the heating temperature of the walls of the vacuum chamber on the KTM tokamak using non-contact methods during plasma discharges. The technical features and placement of the IR diagnostics used in the KTM tokamak are presented. The first experimental results of measuring the heating temperature of the graphite elements of the first wall of the KTM are demonstrated, which showed the operability of the diagnostics under KTM conditions.

A diagnostic method for material transport (erosion and deposition) in the KTM tokamak vessel has been developed and tested for durations comparable to an experimental campaign. It is based on witness samples mounted in the tiles of the first wall of the tokamak vacuum vessel. It was found that the regions of greatest wall erosion are located near the equatorial plane and on the inner side of the upper dome. Deposition zones were identified on the outer periphery on the lower side of the chamber. Possible effects of conditioning and operational discharges on wall sputtering were considered.

The article is devoted to the development of a conceptual design for Thomson scattering diagnostics (TSD) for the KTM tokamak, intended for conducting experimental studies, measuring the dynamics of temperature profiles and the electron concentration of high-temperature plasma. The work shows an extensive literature review of TSD implemented on similar installations. Schemes for plasma probing and collection of scattered laser radiation of TSD are presented. Based on an analysis of the structural features of the KTM tokamak and existing technical constraints, the choice of a tangential diagnostic layout in the equatorial plane has been justified as the most reliable and practically feasible option. Key technical requirements for the Thomson scattering diagnostic system have been defined: an electron temperature measurement range of 50 to 3100 eV, an electron density range of 1·10 ¹⁹ to 2.5·10 ²⁰ m ⁻³ , and coverage of at least 10 spatial observation points. Various diagnostic configurations, including vertical viewing schemes, were analyzed, and their implementation on KTM was shown to be infeasible due to a number of engineering and physical limitations. The proposed configuration ensures alignment stability, protection against parasitic radiation, and high spatial resolution. This work represents a well-substantiated design of a Thomson scattering diagnostic system, the implementation of which will significantly enhance the diagnostic capabilities of the KTM tokamak for plasma and material research under controlled thermonuclear fusion conditions.