Новий композитний матеріал на основі важкого бетону і базальт-борної фібри для радіаційного захисту від нейтронного випромінювання Романенко І.М. Інститут проблем безпеки АЕС НАН України, м. Київ, Україна ORCID: https://orcid.org/0000-0003-0090-8871 Голюк М.І. Інститут проблем безпеки АЕС НАН України, м. Київ, Україна ORCID: https://orcid.org/0000-0001-9233-9287 Носовський А.В. Інститут проблем безпеки АЕС НАН України, м. Київ, Україна ORCID: https://orcid.org/0000-0002-2594-3780 Власенко Т.С. Інститут проблем безпеки АЕС НАН України, м. Київ, Україна ORCID: https://orcid.org/0000-0002-1743-4652 Гулік В.І. Інститут проблем безпеки АЕС НАН України, м. Київ, Україна ORCID: https://orcid.org/0000-0002-3790-8392 Для безпечної експлуатації різних джерел радіоактивного випромінювання необхідно мати надійний радіаційний захист. Захист від радіоактивного випромінювання досліджується дуже давно, як в нашій країні так і за кордоном. Але на сьогодні все ж існує потреба в розробці нових композитних матеріалів, що будуть забезпечувати захист від радіоактивного випромінювання та матимуть покращені механічні та економічні характеристики.Представлено новий композитний матеріал для радіаційного захисту на основі важкого бетону з серпентинітом, армованого базальтборною фіброю, з різними концентраціями оксиду бору, для використання в біологічному захисті в атомній енергетиці. Захисні властивості нового композитного матеріалу були досліджені з різними джерелами нейтронного випромінювання, а саме: 1) нейтрони з енергією 14 МеВ; 2) швидкі нейтрони, що утворюються при поділі U-235 (джерело спектра поділу U-235); 3) швидкі нейтрони поділу U-235 після проходження шару води.Виконано моделювання проходження нейтронного випромінювання в цьому бетоні і в бетоні зі щебенем за допомогою Монте-Карло коду Serpent. Показано, що додавання базальт-борної фібри в бетон покращує захисні властивості бетону від нейтронного випромінювання для нейтронів з різними енергіями, але найбільш ефективним є додавання фібри у випадку теплових нейтронів. К л ю ч о в і с л о в а: базальт-борна фібра, серпентиніт, важкий бетон, радіаційний захист, Монте-Карло код Serpent, моделювання нейтронного випромінювання.
The paper presents a new composite material for radiation shielding properties. This material is based on super-heavy concrete reinforced with basalt fiber, which could be used in biological protection systems for neutron radiation sources. The simulation of the neutron transport in the presented material was performed using the Monte Carlo Serpent code. Two types of heavy concretes were considered in the present paper: 1) with ordinary rubble coarse aggregate and 2) with barite coarse aggregate. For each type of concrete, the basalt fiber with dosage from 1 kg/m3 to 50 kg/m3 was added. The current transmission rates were obtained as a result of the neutron-physical modelling for neutron transport from source to detector through the proposed concrete samples with different thicknesses. The obtained modelling results were analyzed from the viewpoint of effectiveness of the radiation shielding properties. Also, elastic and capture microscopic cross-sections were considered for some isotopes and as a result, some aspects of the radiation shielding properties were clarified. The concrete with ordinary rubble coarse aggregate has better radiation shielding properties in case of low concrete thicknesses due to better neutron scattering on light nucleuses. In contrast to this, the concrete with barite coarse aggregate has better radiation shielding properties in case of high concrete thicknesses due to better neutron absorption. It is shown that the addition of basalt fiber to concrete not only improves its mechanical properties and reduces the number and size of microcracks, but also increases the ability to protect against neutron flux. The proposed composite material could be recommended for use with the following neutron sources: (D, T) neutron generators, plasma focus devices, fusion reactors and fast reactors. This research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract 20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and use of Low-Enriched Uranium in ADS (T33002)” within the project ‘The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products’.
The management of spent nuclear fuel is one of the most pressing problems of Ukraine’s nuclear energy. To solve this problem, as well as to increase Ukraine’s energy independence, the construction of a centralized spent nuclear fuel storage facility is being completed in the Chornobyl exclusion zone, where the spent fuel of Khmelnytsky, Rivne and South Ukrainian nuclear power plants will be stored for the next 100 years. The technology of centralized storage of spent nuclear fuel is based on the storage of fuel assemblies in ventilated HI-STORM concrete containers manufactured by Holtec International. Long-term operation of a spent nuclear fuel storage facility requires a clear understanding of all processes (thermohydraulic, neutron-physical, aging processes, etc.) occurring in HI-STORM containers. And this cannot be achieved without modeling these processes using modern specialized programs. Modeling of neutron and photon transfer makes it possible to analyze the level of protective properties of the container against radiation, optimize the loading of MPC assemblies of different manufacturers and different levels of combustion and evaluate biological protection against neutron and gamma radiation. In the future it will allow to estimate the change in the isotopic composition of the materials of the container, which will be used for the management of aging processes at the centralized storage of spent nuclear fuel. The article is devoted to the development of the three-dimensional model of the HI-STORM storage system. The model was developed using the modern Monte Carlo code Serpent. The presented model consists of models of 31 spent fuel assemblies 438MT manufactured by TVEL company, model MPC-31 and model HISTORM 190. The model allows to perform a wide range of scientific tasks required in the operation of centralized storage of spent nuclear fuel.
The paper presents a new composite material for radiation protection based on extra-heavy concrete reinforced by basalt fiber. Basalt fiber is a new material for concrete reinforcement, which provides improved mechanical characteristics of concrete, reduces the level of microcracks and increases the durability of concrete. Within the scope of present work, the gamma-ray radiation protection properties of concrete reinforced with basalt fiber was modeled. Two types of extra-heavy concrete were used for this paper. The main gamma-ray attenuation coefficients such as mean atomic number, mean atomic mass, mean electron density, effective atomic number, effective electron density, Murty effective atomic number were analyzed with help of WinXCom software. It has been shown that the addition of basalt fiber to concrete does not impair its gamma-ray radiation shielding properties. With increasing the basalt fiber dosage in concrete, the radiation properties against gamma radiation are improved. This research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract 20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and use of Low-Enriched Uranium in ADS (T33002)” within the project “The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products”.
A new composite material with neutron radiation shielding properties is presented. This fiber reinforced concrete material incorporates basalt-boron fiber, with different concentrations of boron oxide in fiber, and is applicable to nuclear energy and nuclear waste management. The methodology for production of boron oxide (B2O3) infused basalt fiber has been developed. First experimental samples of basalt boron fiber containing 6% of B2O3 and 12% B2O3 have been produced in laboratory conditions. The concrete samples reinforced by two types of basalt-boron fiber with different dosages have been prepared for neutron experiment. The neutron experimental investigations on radiation shielding properties of concrete reinforced by basalt-boron fiber have been performed by means of Pu-Be neutron source. The prepared samples have been tested in the course of several series of tests. It is shown that basalt-boron fibers in concrete improve neutron radiation shielding properties for neutrons with different energies, but it appears to be most effective when it comes to thermal neutrons.
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