In this work, to assess the radiation damage of beryllium under low-temperature neutron irradiation, samples from beryllium grade TShG-200 with an oxide phase concentration of about 1 wt % were studied, which were kept in the IVG.1M research reactor for a long time and were irradiated to fluences 0.8–4·1020 neut./cm2. Also, unirradiated original witness samples of the same brand were tested to compare the results.The aim was to establish the level of radiation degradation of beryllium samples during their tests in the IVG.1M reactor. Mechanical tests for three-point bending and tension were performed to determine the strength of beryllium samples, and their microhardness was also measured. To determine the degree of swelling of the beryllium samples their densities were measured by the method of hydrostatic weighing in the medium of distilled water.According to the results of short-term bending and tensile tests, it was found that the beryllium material after reactor irradiation softens in the range of 9.3–16.7%. And the results of measuring the microhardness showed an increase of up to 23%. Density results did not reveal swelling of the samples after low-temperature neutron irradiation.After mechanical tests, special studies of fractures and microstructural analysis were carried out, which did not reveal noticeable changes in the microstructure of beryllium after irradiation.

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This article describes experimental investigations to determine the corrosion compatibility of candidate matrix materials of a capillary-porous structure (CPS) with a liquid tin-lithium alloy at high temperatures. The studies were conducted with the Sn75-Li25 alloy and samples of 12Ch18Ni10Ti grade austenite stainless steel, VEL-3 grade vanadium, and TT grade tantalum. Experiments on the interaction of a liquid tin-lithium alloy with candidate samples of the CPS matrix at high temperatures were carried out on an experimental TiGrA setup based on a TGA/DSC 3+ thermogravimetric analyzer. The paper provides a description of the methodology and conditions for conducting high-temperature corrosion tests. In the course of this work, experiments were carried out to study the compatibility of a tin-lithium alloy in the liquid phase with a stainless steel, vanadium and tantalum samples in the temperature range from 600 ℃ to 1000 ℃. Based on obtained results, the thermal effects of the processes occurring as a result of the interaction of the alloy with a candidate materials of the CPS matrix were determined. As a result of the analysis of the results obtained it has been revealed that at interaction of the studied materials with liquid tin-lithium alloy Sn75-Li25 at high temperatures complex physical and chemical processes take place, such as: selective dissolution of components by liquid alloy (solvent); penetration of component of liquid alloy (tin) into stainless steel depth; mass transfer of dissolved metals from solid metal into liquid.

The paper presents the results of the development and manufacture, as well as assembly and installation of a test device for testing miniature samples by the SPT method. The results of mechanical tests by tensile and SPT methods of 35X steel material after heat treatment (quenching + tempering) at different tempering temperatures. The evaluation of changes in the strength characteristics of steel grade 35X, depending on the heat treatment mode. The correlation equations between the t/10 method and the yield strength of each 35X steel sample obtained during tensile tests were determined and obtained.