Attenuation of Neutron and Gamma Radiation from Radioisotope Sources by Material Based on Modified Titanium Hydride

Inorganic Materials: Applied Research. 2022. Vol. 13. No. 2. P. 357–364.

Yastrebinsky R. N., Bondarenko G.G., Karnauhov A. A.

The paper presents experimental studies of the radiation-protective properties of a material based
on a modified titanium hydride with respect to gamma and neutron radiation of point radioisotope sources
in barrier and continuous protection geometries. The calculation models of the problem of solving the radiation
transport equation for the Monte Carlo method and a comparative assessment of experimental and calculation
results are given. The assessment of the amplitude distribution of gamma radiation in the thickness
of the material of protection showed a significant reduction in the power of the equivalent dose of gamma
radiation in the energy range of 180–250 keV, which is due to the Compton scattering effect. The relaxation
length of the dose of γ radiation in 137Сs by the protective material was 4.80 ± 0.18 cm. The relaxation length
of the flux of fast neutrons from the Pu-α-Be source was 6.20 ± 0.18 cm. Comparative analysis of the experimental
and calculation data of the protective properties of the material based on modified titanium hydride
in relation to radioisotope sources has shown high convergence of the results obtained and the adequacy of
the application of the calculation model of the task for the MCNP program used.

Keywords: гидрид титана, radioisotope sources, радиоизотопные источники, Neutron and Gamma Radiation, Titanium Hydride, нейтронное и гамма-облучение