The interaction of peripheral D–Li-plasma with the protective ceramic elements of electrical porcelain, EP (xAl2O3⋅ySiO2), on the limiter of the T-11M tokamak has been studied. The calculated theoretical estimate of the maximum possible lithium capture is 6 mg (5 μg/discharge). The authors’ experimental method, based on the acid leaching with formic acid of the products of the interaction of EP with elemental lithium from the surface of dismantled protective ceramic elements, allowed us to obtain a practical estimate of Li-sorption equal to 3 mg (2.5 μg/discharge) ( 50
The SMOLA facility was built at the Institute of Nuclear Physics, Siberian Branch of the Russian Academy of Sciences (INP SB RAS) to experimentally test the concept of helical confinement. This method is a development of the multiple‑bounce confinement scheme. A stream of rotating plasma flows out of the open trap through a magnetic field with helical symmetry that is periodically modulated along the field line. Confinement efficiency depends strongly on the ratio of the ion mean free path to the period of the magnetic‑field modulation. Experiments on the SMOLA facility confirmed improved plasma confinement both in the regime dominated by Coulomb collisions and at reduced collision frequency. Simulation of plasma flow regimes for next‑generation facilities requires a further reduction of the dimensionless Coulomb collisionality. For this purpose a SMOLA* installation is being constructed at INP SB RAS. The paper discusses the new magnetic configuration with mirror‑symmetric helical end‑plugs, an auxiliary ion‑cyclotron resonance (ICR) heating system, methods for generating plasma rotation, and features of the diagnostic suite.
During the work on integrating the diagnostics into the ITER ports, a problem arose with providing the required radiation protection. It was proposed that a large amount of a neutron-absorbing material, boron carbide, be placed in the vacuum chamber in the port plug. The chemical composition and the thermal and vacuum properties of various B4C ceramics from several manufacturers were studied. Sintered ceramics in the form of blocks with holes were selected. A specification for the production of ceramics for ITER ports was agreed upon. Experiments on irradiation of ceramics with neutrons at the VITA accelerator were carried out. The degradation of mechanical properties after prolonged fast neutron irradiation was investigated. Serial production of sintered ceramics was started. The ITER Organization has approved the End of Manufacturing reports on the serial batches of ceramics.
Tokamak T‑15MD gradually reaches the design parameters. At the moment, an important task is to obtain stable discharges with diverter configurations and a plasma current of at least 500 kA with a pulse duration at the quasi‑stationary stage of the order of 1 s. To effectively solve this problem, it is necessary to support the experiments with numerical modeling both in the interval between the experimental campaigns and directly during the campaign. The use of numerical analysis of experiments in the 2025 T‑15MD campaign made it possible to optimize plasma discharge scenarios and work out an active feedback system in relation to the vertical and horizontal displacements of the plasma column. Stable discharges were obtained with a diverter and a plasma current of 500 kA and a duration at the quasi‑stationary stage of the order of 1 s. The paper summarizes the experimental experience and numerical calculations obtained during the spring campaign of 2025 and provides recommendations for obtaining one of the discharge scenarios with a diverter on the T‑15MD tokamak unit.
The article describes a method for controlling the geometric parameters of the cooling system channels of the diagnostic shielding modules of the equatorial port no. 11 of the ITER nuclear installation made using counter deep drilling technology. The technique is based on the use of an angular reflector moving through the test channel and a laser tracker. The results of the qualification of the methodology on a full-size test product modeling the deepest channels in the diagnostic shielding module are presented.
