[en] Investigations of the influence of carbon and hydrocarbon layers on the trapping and reflection of hydrogen isotopes by tungsten were carried out with BCA based computer code SCATTER. It is shown that for small layer thickness the trapping efficiency depends on the hydrocarbon film composition. At layer thickness of a few nanometers energy dependence of the trapping efficiency has a non-monotonous character with a minimum at primary energies about 100-1000 eV and continuous increment with energy at higher energies. The possible reason of this effect is briefly discussed. Comparison between the trapping efficiencies of different hydrogen isotopes in a C-W target is also presented

[en] Trapping of low energy deuterium ions is investigated at inclined ArD⁺ bombardment of Nb target. The trapping coefficient η, which is found from the thermal desorption spectra after implantation, is measured for the energy range of 5-120 eV per deuteron at 60 deg. angle of incidence. The value of η measured for target cleaned with Ar bombardment and temperature treatment decreases with energy from η∼0.3 at the primary energy E₀=120 eV to η∼0.15 at about E₀=5 eV. Computer simulations based on the binary collision approximation and performed with taking into account the real target micro relief measured with STM agree with the experimental data rather well

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[en] The method of defects creation in thermonuclear reactor materials by high-energy electrons irradiation is tested. For this purpose module for irradiation with water-cooled specimen holder is made. The experiment of tungsten samples irradiation by 10 MeV electrons with 5×10¹³ e/s×cm² flux density up to 7×10¹⁸ e/cm² dose is carried out. Computerized simulation of defects distribution showed their uniform distribution in the sample at the level of 4×10^-4 dpa. The level of damages on the reverse side of sample is approximately twice as little as that on the input one. It is pointed out that the samples with defects of such type and level can be used for studying fundamental processes of hydrogen isotopes accumulation in defects of thermonuclear reactor materials

[en] Full text: In the next step fusion devices, such as DEMO or fusion neutron sources high neutron fluxes and fluences are expected. In this case reduce activated (RA) and heat-resistant structural materials should be used. In Russia V-(4–10) Ti-(4–10) Cr alloys, austenitic and RA ferritic-martensitic steels for fission applications are developed and manufactured in A. A. Bochvar High-technology Research Institute of Inorganic Materials. For using materials in next step fusion devices additional studies should be done. Interaction of hydrogen isotopes with structural material is one of the important factors, determining the possibility of using this material in fusion reactors. Permeation of hydrogen isotopes through structural material is one of the key characteristic as tritium is the component of fusion fuel available only in small quantities, expensive and radioactive. In the present work gas-driven permeation (GDP) and plasma-driven permeation (PDP) through ferritic-martensitic steel RUSFER-EK-181 (Fe-12 Cr-2W-V-Ta-BC), austenitic steel ChS-68 (used in fast breeder reactor BN-600 as cladding) and V-4 Ti-4 Cr were investigated using the PIM facility (at NRC “Kurchatov Institute”). In the experiments RUSFER-EK- 181 and ChS-68 tubes of 250 mm length with diameter of 6.85 mm and wall thickness of 0.4 mm (effective area 50 cm²) and flat V-4 Cr-4 Ti membrane with diameter of 50 mm and thickness of 0.1 mm (effective area 20 cm²) were used. The PIM facility is equipped with a distributed ECRH plasma source, which was used for cleaning the inlet sample surfaces by argon ions with ion energy 300 eV and for deuterium plasma irradiation in PDP measurements (typical ions flux density is 10 A/m² at accelerating potential of -300 V). Deuterium GDP measurements were performed in the pressure range of 5 x 10^-2–100 Pa and in the temperature range of 600–900 K. At GDP permeability coefficient of V-4 Cr-4 Ti membrane is about four orders of magnitude higher than that of RUSFER-EK-181 while permeability coefficient of ChS-68 is higher than permeability coefficient of RUSFER-EK-181 at all pressures and temperatures. However V-Cr-Ti alloys are promising materials for a membrane pump as a superpermeable metal membranes that can be used for provide a significant compression for hydrogen and a 100% separation of fuel from He and other impurities. (author)

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[en] In next-step fusion devises (DEMO reactor and hybrid fusion-fission reactor) neutron fluxes and resulting damage of materials will be significantly higher than in ITER. The tritium decay will lead to formation of radiogenic helium in the bulk of plasma-facing and constructive materials. These processes will lead to structure changes of materials and will influence tritium retention. The aim of the project is to model experimentally damages in fusion facilities and investigate their influence on hydrogen retention in RAFMs. One of the main goals is to investigate influence of radiogenic He formation on deuterium retention afterwards.

[en] Using the method of thermodesorption spectroscopy (TDS) the capture of deuterium ions by tungsten and rhenium alloys, which are considered candidate materials for a thermonuclear reactor, is studied. Alloys of different structures with different rhenium content were irradiated with 200 eV/D deuterium ions by doses ranging from 10²² to 10²⁴ D/m². In the TDS spectra a high-temperature peak at temperature 850 K was revealed, which was attributed to deuterium capture in gas-filled cavities of the alloy. During annealing of the alloys studied, as well as during their high-dose irradiation by low-energy deuterium ions, the effect of the cavities healing in the bilk of the material was observed. It has been ascertained that the alloy structure affects essentially the capture of deuterium with W-Re alloys, while rhenium content effect is actually negligible

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