Том 50, № 4 (2024)

Мұқаба

Бүкіл шығарылым

TOKAMAKS

ITER and TRT—Technological Platforms for Controlled Thermonuclear Fusion

Krasilnikov A.

Аннотация

To solve the main problems of designing a thermonuclear tokamak reactor, such as the experimental demonstration of quasi-stationary thermonuclear burning, generation of non-inductive quasi-stationary current; development of plasma technologies and materials of the first wall and divertor, the International Thermonuclear Experimental Reactor ITER is being designed, projects of DEMO demonstration reactors are being developed, and a Tokamak with Reactor Technologies TRT is being developed in Russia. The main components of the ITER (superconducting electromagnetic system (EMS) made of Nb3Sn and NbTi, the first wall of W coated with a low-Z material, systems for additional plasma heating, experimental modules of a breeder blanket, plasma control systems, etc.) and TRT (EMS of high-temperature superconductors, first wall options of W with B4C coating, TiB2–AlN composite and liquid metal lithium, additional heating and quasi-stationary non-inductive current drive systems, innovative divertor, experimental breeder and hybrid blanket modules, reactor-compatible diagnostics and remote plasma control systems, etc.) technology platforms are presented. The technological platforms of the ITER being under construction and the TRT being designed contain an almost complete, according to modern understanding, set of technologies for the future thermonuclear reactor.

Fizika plazmy. 2024;50(4):363-372
pages 363-372 views

Complex for Thomson Scattering Diagnostics on the TRT Tokamak

Mukhin E., Tolstyakov S., Kurskiev G., Zhiltsov N., Ermakov N., Tkachenko E., Koval A., Solovey V., Aleksandrov S., Nikolaev A., Antropov D., Bondar A., Kedrov I., Marchenko T., Kornev A., Makarov A., Bogachev D., Samsonov D., Guk E., Klimov V., Smirnova E., Sotnikov A., Razdobarin A., Bazhenov A., Bocharov I., Bocharnikov V., Bukreev I., Dmitriev A., Elets D., Tereshchenko I., Varshavchik L., Chernakov A., Pankrat’ev P., Marchii G., Minbaev M., Nikolaenko K., Kungurtsev N., Sakharov N., Petrov Y., Mokeev A.

Аннотация

A diagnostic system for Thomson scattering of the central, edge and divertor plasma regions of a tokamak with reactor technologies is discussed. The rationale and choice of technical solutions are given, the composition of the Thomson scattering diagnostic complex is discussed, as well as an estimate of the accuracy of measuring the electron temperature and plasma density in the central edge and divertor regions of the TRT tokamak. Particular attention is paid to ensuring the functionality of the proposed diagnostics in the reactor mode of the tokamak operation and the results of testing diagnostic equipment in experiments on the Globus-M2 tokamak.

Fizika plazmy. 2024;50(4):373-389
pages 373-389 views

Concept of a Diagnostic System for Measuring the Electron Temperature Profile of Plasma from the Intensity of Electron Cyclotron Emission for the TRT Facility

Solovev N., Dias Mikhaylova D.

Аннотация

The paper presents a concept of the ECE diagnostic for the TRT facility and estimates the achievable measurement parameters in the baseline scenario. The target spectral region for the diagnostic corresponds to the first harmonic of the ECR frequency in ordinary polarization (O1) and the second harmonic in extraordinary polarization (X2). It is proposed to carry out measurements from the low-field side along two lines of sight: radial and toroidally oblique. The accessible spectral region in terms of the normalized radial coordinate is approximately estimated as –0.9 to 0.9 and –0.1 to 0.9. It is proposed to shape the input wave beam by means of a quasi-optical focusing system that provides a transverse size of the resolved region of approximately 3—5 cm for O1 and 1.2—3 cm for X2. For measurements, it is proposed to use Fourier transform spectrometers with a time resolution of about 10 ms and multichannel heterodyne receivers with a time resolution of about 1 μs. The minimum radial size of the resolved region is estimated to be 3—5 cm for O1 and 2—4 cm for X2, depending on the coordinate.

Fizika plazmy. 2024;50(4):390-408
pages 390-408 views

Conceptual Project for Diagnostics of Erosion of the First Wall and Divertor of the Tokamak with Reactor Technologies TRT

Razdobarin A., Shubin Y., Belokur A., Bogachev D., Elets D., Medvedev O., Mukhin E., Snigirev L., Alekseenko I.

Аннотация

A conceptual design for diagnosing erosion of the first wall and divertor plates of a tokamak with reactor technologies TRT is proposed. The principles of constructing a diagnostic complex based on the following systems are developed: laser radar, dual-wavelength digital holographic interferometry and active laser IR thermography. An optical scheme is developed for combining the optical paths to input laser radiation and collect scattered light from diagnostic systems. To view the maximum area of the first wall, a scheme for optical scanning of the surface of the first wall and divertor is proposed. Based on optical simulation, the spatial distribution of the power density and phase of interferometry laser radiation in the illuminated region of the first wall is constructed, and the dimensions of the light fields and power density for IR thermography and laser radar diagnostics are determined. An image formation scheme is proposed and the spatial resolution is determined for interferometry and IR thermography methods. The light scattering function on models of the ITER divertor cladding is studied experimentally. The energy of the collected signal is calculated on the basis on the experimental data for all three diagnostic methods and the requirements for the diagnostic equipment are formulated.

Fizika plazmy. 2024;50(4):409-426
pages 409-426 views

Simulations of TRT Vacuum Vessel Effect on the Magnetic Diagnostics System Sensor Signals

Belov A., Andreev V., Sushkov A.

Аннотация

The results of model numerical calculations are presented, showing the effect of the TRT vacuum vessel on the amplitudes and phases of the magnetic sensors signals, which are located on the inner and outer vacuum vessel surfaces. It is shown that the characteristic times of loop voltage sensors considerably depend on their position on the TRT vacuum vessel. Therefore, their accurate mutual matching is required, especially in the dynamic stage of the discharge, when high eddy currents are induced in the vacuum vessel. The results of numerical calculations for the case of periodic disturbances in the plasma column are presented. They showed that the vacuum vessel almost completely shields the signals of the magnetic sensors located on the outer surface of the vacuum vessel. Moreover, it affects not only the amplitudes of magnetic sensors signals, but also their phases. Numerical studies brought us to conclusion that it is of priority to install the magnetic sensors just on the inner surface of the TRT vacuum vessel.

Fizika plazmy. 2024;50(4):427-441
pages 427-441 views

The Concept of the MSE Diagnostic at the TRT Tokamak Facility

Zemtsov I., Neverov V., Nemets A., Krupin V., Pshenov A., Davydenko V., Stupishin N.

Аннотация

The possibility of carrying out measurements of plasma parameters in a tokamak with reactor technologies (TRT) by means of the technique based on the Stark effect by resolving the spectrum of the split lines of Balmer series emitted by fast hydrogen atoms injected into plasma is analyzed. The code containing the models of emission applicable for the high-temperature tokamak plasma, along with the library of functions for the ray-tracing simulation of geometric optics, was used. Simulation of spectra of active neutral beam emission and plasma emission, both as a result of charge exchange on beam atoms and passive one, taking into account reflections from the plasma facing vessel elements, allowed determining parameters of the diagnostic injector and relative position of the light-collection systems and heating injectors for which the useful and background spectra could be separated. The signal gathered by the detector is simulated. The shape of the visual angle along the line of sight, optical properties of the lens materials, the instrumental function of the spectral device, the sensor characteristics, and statistical noise of the signal are taken into consideration. Based on the obtained results, a preliminary concept of the motional Stark effect (MSE) diagnostic for the tokamak with reactor technologies is proposed.

Fizika plazmy. 2024;50(4):442-467
pages 442-467 views

Concept of the Doppler Backscattering Diagnostic on TRT

Yashin A., Ponomarenko A., Solokha V., Rozhkov S., Kharchevskii A.

Аннотация

The paper discusses the possibility of using the Doppler backscattering (DBS) diagnostic to aid the Tokamak with Reactor Technologies (TRT) with its mission, and also offers ways of installing it in TRT, including the possible technical characteristics of the system. One of the most important advantages of DBS implementation is the ability to investigate various areas of plasma. This requires selecting an appropriate range of probing frequencies to match the scenarios and density profiles expected in TRT. Aspects and advantages of different ways of implementing DBS in the tokamak are discussed. Possible hardware, design and arrangement of the antenna system are presented. There are also system limitations that need to be considered specifically for TRT. The propositions for DBS on TRT are supported by calculations of ray tracing and diagnostic resolution. The wave number values of plasma fluctuations that the system could detect are also estimated.

Fizika plazmy. 2024;50(4):468-483
pages 468-483 views

Study of the Method of Photon Neutralization of Powerful Beams of Negative Ions at the Budker Institute of Nuclear Physics

Popov S., Atlukhanov M., Burdakov A., Ivanov A., Kurkuchekov V., Sanin A., Skovorodin D., Trunev Y., Shikhovtsev I.

Аннотация

A short review of the studies carried out at the Budker Institute of Nuclear Physics, Siberian Branch, Russian Academy of Sciences (BINP SB RAS) on the photon neutralization of the beams of negative ions is presented. The principal distinctive feature of the presented approach consists in the nonresonant accumulation of photons in a limited space. Their confinement is based on the adiabatic motion of photons in a system of concave mirrors, which is insensitive to the quality of the injected radiation. An analysis is carried out of the possibility of using the neutralizer based on such a nonresonant photon trap in large-scale installations such as ITER and TRT, and a future experiment is described on the photon neutralization using a beam of negative hydrogen ions with energy up to 130 keV and a current of about 10 mA.

Fizika plazmy. 2024;50(4):491-501
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Possibilities of Using Active Neutral Particle Diagnostics at the TRT Facility

Afanasyev V., Melnik A., Mironov M., Navolotsky A., Nesenevich V., Petrov M., Petrov S., Chernyshev F., Shmitov R.

Аннотация

The possibilities of using active neutral particle diagnostics for measuring local ion temperatures and isotopic ratio of deuterium-tritium plasma at the tokamak with reactor technologies are considered. Options for positioning the neutral particle analyzer relative to the diagnostic injector are presented. The fluxes of deuterium and tritium atoms escaping out of plasma were simulated in a wide range of plasma densities and temperatures. It is shown that the neutral particle analyzer active diagnostics will make it possible to measure the plasma parameters mentioned with the spatial and time resolutions of ~14 cm and ~0.01—0.1 s, respectively.

Fizika plazmy. 2024;50(4):502-508
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Spectrometers of Neutrons and Fast Atoms of Tokamak Thermonuclear Plasma Based on CVD Synthesized Diamond Single-Crystal Films

Kirichenko A., Krasilnikov A., Rodionov N., Rodionova V., Trapeznikov A., Yartsev V., Meshchaninov S., Artemev K., Khmel’nitskii R., Amosov V.

Аннотация

High radiation resistance, chemical inertness, the ability to operate at elevated temperatures, high mobility and efficiency of charge-carrier collection are important properties of diamond for designing detectors and spectrometers of ionizing radiation. Currently, diagnostics of neutrons and neutral particle fluxes based on diamond detectors for the ITER thermonuclear reactor are justified and developed. This work presents the results of a Raman spectroscopy and photoluminescence spectroscopy study of the electronic quality of synthesized epitaxial diamond films obtained by vapor deposition in a hydrogen and methane mixture in the ARDIS reactor on boron-doped single-crystal diamond substrates. To confirm their electronic quality, detectors have been made from films selected by spectrometric methods and the charge collection efficiency and energy resolution have been measured when irradiated with alpha particles from a 241Am source and 14.7 MeV fast neutrons from the ING-07T2 neutron generator.

Fizika plazmy. 2024;50(4):484-490
pages 484-490 views

Options for Implementation of IR Thermography Diagnostics in a Tokamak with Reactor Technologies TRT

Razdobarin A., Shubin Y., Bogachev D., Elets D., Medvedev O., Mukhin E., Snigirev L.

Аннотация

AbstractOptions for implementing the IR thermography diagnostic system in a TRT facility are considered. Two variants of the optical scheme for measuring the temperature of the first wall and divertor targets are proposed: a wide-angle system combined with two divertor channels and a four-channel viewing system. The optical resolution of both systems and the levels of the collected signal are numerically simulated. On the basis of the calculations performed, conclusions are drawn about the compliance of the systems with the requirements for measuring the temperature of TRT plasma-facing elements. The sources of the temperature measurement error are considered, and the error caused by the reflection of radiation from structural plasma-facing elements by the surface under study is estimated. Calibration issues for IR thermography diagnostics are also discussed.

Fizika plazmy. 2024;50(4):509-520
pages 509-520 views