Authors & Affiliations
Minnebayev M.I., Belozerova A.R., Pavlov V.V., Chernysheva T.I.
Research Institute of Atomic Reactors, Dimitrovgrad, Russia
Minnebaev M.I. – Engineer.
Belozerova A.R. – Senior Researcher, Cand. Sci. (Phys.-Math.). Contacts: 9, Zapadnoye shosse, Dimitrovgrad, Russia, 433510. Tel.: +7 (84235) 9-87-58, 7-98-43; e-mail:
Pavlov V.V. – Lead Engineer.
Chernysheva T.I. – Lead Engineer.
Abstract
In search of new materials for nuclear technologies the authors of the article studied samples of natural rock mica. Mathematical models for determining classification attributes of tested materials comparable to each other have been considered to simulate absorption properties of materials against neutron and gamma radiation in a pneumatic conveying pilot plant and based on simulation of neutron and gamma ray tracks in three-dimensional geometry. A model educated on experimental data with an accuracy of its predictions not worse than 10 % was accepted as a valid model and was used to calculate each of the dependencies for protective layer thicknesses up to 30 cm. The neutron flux density distribution in a tray filled with different shielding materials at different tray surroundings is calculated by the Monte Carlo method. Experimental and theoretical evaluations of the shielding properties of the material investigated have found its potential for use in the construction of a fourth-generation reactor. In perspective it is preferable to use natural rock mica for biological shielding from gamma rays when impregnating it with special substances with high density of elements of high atomic number, such as lead, bismuth, tantalum, tungsten, or for biological shielding from neutrons of different energy by impregnation with boron elements during technological processing of this porous material. Its use for combined shielding against fast neutrons in the laboratory is not excluded.
Keywords
ionizing radiation, biological shield materials, simulation and mathematical modeling, neutron radiation absorption, gamma radiation absorption
Article Text (PDF, in Russian)
UDC 621.039.53
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 1, 1:14