Search academic texts

Information × Registration Number 0221U106991, 0120U101256 , R & D reports Title Development and research of principally novel structural materials with guided structure for operational and future reactors to enhance the safety and economy of nuclear power popup.stage_title Head Voyevodin Viktor Mikolayovich, Доктор фізико-математичних наук Registration Date 24-12-2021 Organization National Science Center "Kharkiv Institute of Physics and Technology" popup.description2 The thermodynamic and kinetic features of the interaction of hydrogen and helium isotopes with FeCrAL alloys, tungsten and protective coatings from these materials have been investigated. Sputtering yields and changes in the surface morphology of FeCrAl coatings were determined. Sputtering yields are compared with existing published data for Fe, Cr and W. Thermal desorption spectroscopy was used to determine the deuterium contained in the bulk of the tungsten, 18Cr10NiTi (ODS) and 18Cr10NiTi steels. A calculated estimate of the desorption of deuterium within the framework of the diffuse capture model made it possible to relate the characteristics of the experimental TD spectra with specific capture centers in the material. The maximum swelling of chromium coatings was observed at an irradiation temperature of 500 ° C and amounted to 1.6%, which is significantly lower than the permissible value of swelling (~ 5%) for reactor materials and indicates a high radiation resistance of chromium coatings at irradiation doses up to 25 digits. The swelling for the oxide dispersion-hardened steel 18Cr10NiTi (ODS) was determined to be half (4.8%) compared to ordinary steel 18Cr10NiTi (9.4%), which indicates an improved resistance to swelling of ODS steel. ODS steel is less prone to radiation strengthening / brittleness. It was found that the main strengthening effect is caused by gas cavities.   Product Description popup.authors Karpov Sergiy O Kuprin Oleksander S Tikhonovsky Mikhail A popup.nrat_date 2022-03-09 Close