The article presents the results of measuring the parameters of the amplitude-frequency characteristics (AFC) of the antenna module circuit of the system for additional high frequency (HF) heating of the KTM tokamak plasma in laboratory conditions. A description of the antenna-feeder device and the HF system of the KTM tokamak is presented. At this stage of time, commissioning works for launching of the HF system of additional heating are performed at the KTM tokamak. The design and launch of such system requires conducting of separate research. Since the HF system consists of four modules, which includes various subsystems and components, before testing the entire HF system as an assembly, it is necessary to check and determine the parameters of individual components of the HF system. The antenna module is a part of the antenna-feeder device and is a very important component in the HF system, because it transfers energy from the generator to the tokamak plasma, thus heating the plasma. In case if the transmitting system does not match the declared operating frequency, HF system will be mismatched, which will affect the efficiency of plasma heating and operation of the entire HF system. It is impossible to bring the KTM tokamak to the nominal declared power without putting into operation of the system for additional HF heating of the plasma. Additional components are attached to the antenna module, the influence of which must also be studied for the correct operation of the entire HF system in the future. This paper presents a method for measuring the frequency response of the antenna module and the results of determining the operating parameters of the antenna module such as: wave impedance, inductance, capacitance, resonant frequency and quality factor of the antenna module circuit, depending on various additional inductance adjustment elements. В статье представлены результаты измерения параметров амплитудно-частотных характеристик (АЧХ) контура модуля антенного системы дополнительного высокочастотного (ВЧ) нагрева плазмы токамака КТМ в лабораторных условиях. Представлено описание антенно-фидерного устройства и ВЧ системы токамака КТМ. На данном этапе времени на токамаке КТМ проводятся пуско-наладочные работы по введению в строй ВЧ системы дополнительного нагрева. Проектировка и запуск подобной системы требуют проведения отдельных научно-исследовательских работ. Так как ВЧ система состоит из четырех модулей в состав которого входят разнообразные подсистемы и узлы, то перед испытанием всей ВЧ системы в сборе, необходимо проведение работ по проверке и определению параметров отдельных узлов ВЧ системы. Антенный модуль входит в состав антенно-фидерного устройства и является очень важным элементом в ВЧ системе так как именно он осуществляет передачу энергии от генератора в плазму токамака, таким образом осуществляя нагрев плазмы. В случае если передающая система не будет согласована на заявленную рабочую частоту, то ВЧ система будет рассогласованной, что повлияет на эффективность нагрева плазмы и работу всей ВЧ системы в целом. Без ввода в эксплуатацию системы дополнительного ВЧ нагрева плазмы невозможен вывод токамака КТМ на номинальные заявленные мощности. К антенному модулю прилагаются дополнительные элементы влияние которых также необходимо изучить для корректной работы всей ВЧ системы в будущем. В данной работе приведены методика измерения АЧХ модуля антенного и результаты определения рабочих параметров модуля антенного таких как: волновое сопротивление, индуктивность, ёмкость, резонансная частота и добротность контура модуля антенного в зависимости от различных дополнительных элементов подстройки индуктивности. Мақалада КТМ токамагы плазмасының қосымша жоғары жиілікті (ЖЖ) қыздыру жүйесінің антенналық модулі контурының амплитудалық-жиіліктік сипаттамаларының (АЖС) параметрлерін зертхана жағдайларында өлшеу нәтижелері ұсынылған. КТМ токамагының антенналық-фидерлік құрылғысы мен ЖЖ жүйесінің сипаттамасы ұсынылған. Уақыттың осы кезеңінде КТМ токамагында қосымша қыздырудың ЖЖ жүйесін қатарға қосу бойынша іске...

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.

This paper presents the results of experiments on the research of gas release from graphite tiles in a KTM tokamak. The methodology of the experiment and the design of the experimental vacuum stand are described in detail. The dependences of the gas release from graphite tiles over time during their annealing to a temperature of 200 ℃ with constant pumping using a high-vacuum pump, simulating the annealing conditions in a KTM vacuum chamber, are presented. The work also includes a mass spectrometric analysis of the composition of the vacuum medium in the vacuum chamber of the experimental stand before heating and after cooling the vacuum chamber (VC). An analysis of experimental data is presented and estimates of the maximum residual pressure in the KTM VC are given.

This paper presents the results of the first experimental tests of the ion cyclotron radio-frequency (RF) plasma heating system of the KTM tokamak with an equivalent plasma load. Measurements of the operating parameters of the RF generator and the antenna-feeder system were carried out under conditions approximating plasma operation. The generator circuits were tuned and matched to the load, and the generation characteristics as well as the conditions for stable RF power transmission to the load were investigated. Stable operating regimes of the system and the conditions ensuring stable RF power generation were determined. The test results confirm the functionality of the main components of the RF heating system and demonstrate the possibility of further testing with plasma in the KTM tokamak.

In this paper, a literature review on the application and features of boronization in tokamak-type devices is presented, and a methodology for preparing the vacuum chamber of the KTM tokamak for plasma experiments using a carboranebased boronization system is substantiated. The technical implementation of the process under glow discharge conditions is described, including the design of the vapor delivery system with a heated receiver and the transport line on the KTM tokamak. A project of the diagnostic complex under development for real-time monitoring of the environment purity, combining mass spectrometry and optical monitoring of the boron emission line, is presented.

In the Kazakhstan Material Testing Tokamak (KTM), additional plasma heating will be achieved by injecting power in the ion cyclotron resonance frequency range using four identical generators, each delivering 2 MW of output power. Prior to transitioning the KTM into regular operation, it is necessary to tune these generators using a load equivalent that simulates plasma-like operating conditions. This article presents the electrodynamic design and analysis of a load equivalent capable of absorbing up to 2 MW of high-frequency power. The geometry and key parameters of the load equivalent for the additional high-frequency (HF) plasma heating system of the KTM tokamak are defined. The calculations are based on the assumption that the optimal solution is to construct the load equivalent as a resonator containing a saline aqueous solution absorber housed in a tank with a dielectric window. A dielectric material with high permittivity is proposed for use in the resonator structure. The results demonstrate that the developed load equivalent enables effective testing and tuning of the high-power generators, thus ensuring the readiness of the additional power injection system for scheduled activation on the KTM tokamak. Two plasma load equivalent (PLE) configurations were investigated for different bench-testing purposes. The large PLE was optimized for high RF power absorption in the standing-wave regime, whereas the small PLE was designed to provide a low-impedance loading condition for antenna-matching tests in preparation for plasma operation.