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Information × Registration Number 0222U005238, 0121U109337 , R & D reports Title Development and study of new composite materials based on heavy concrete and basalt-boron fiber with improved radiation shielding properties for nuclear energy popup.stage_title Head Nosovskyi Anatolii V., Доктор технічних наук Registration Date 26-12-2022 Organization Institute for Safety Problems of Nuclear Power Plants of the National Academy of Sciences of Ukraine popup.description2 The object of research is radiation-shielding concrete for the production of containers for long-term storage of spent nuclear fuel. The purpose of the work is to develop a recipe for special concrete that meets the requirements for manufacturing containers for long-term storage of spent nuclear fuel. Research methods – determination of physical, mechanical and thermophysical properties of special concrete, assessment of durability of concrete, creation of a calculation model of a container for long-term storage of spent nuclear fuel. The composition of radiation-shielding concrete was selected, and the physical and mechanical tests of experimental samples of concrete were carried out. According to the results of the research, concrete recipes were provided, the results of compressive strength tests of experimental samples were obtained, the concrete application temperature was justified, and the durability of the obtained concrete was evaluated. An analysis of literature data was carried out, in which the results of experimental studies of the influence of neutron and gamma irradiation on the mechanical characteristics of concrete (such as compressive strength, tensile strength when bending, modulus of elasticity, change in volume and change in dimensions) are given. According to the results of the research, a predicted assessment of the durability of concrete was made. A description of the calculation model of the HI-STORM container with a loaded multi-purpose container -31 is presented. The model was created using the Serpent neutron physics Monte Carlo code, which is an analogue of the MCNP code. Product Description popup.authors Holiuk Maryna I. Gulik Volodymyr I. Kutsyn Pavlo M. Romanenko Iryna M. Trofymenko Oleksandr Ruslanovych Khotyayintseva Olena Mykolayivna popup.nrat_date 2022-12-26 Close
R & D report
Head: Nosovskyi Anatolii V.. Development and study of new composite materials based on heavy concrete and basalt-boron fiber with improved radiation shielding properties for nuclear energy. (popup.stage: ). Institute for Safety Problems of Nuclear Power Plants of the National Academy of Sciences of Ukraine. № 0222U005238
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Updated: 2026-03-22