Многогрупповое моделирование защиты от нейтронного и гамма излучения материалами на основе гидрида титана

Abstract

The paper presents calculated data on a comparative assessment of the radiation-protective properties of materials based on titanium hydride, obtained by the method of multigroup modeling of protection against neutron and gamma radiation. Two types of compositions behind the steel reactor vessel and lead shielding are considered. It is shown that gamma radiation behind the protection of titanium hydride is formed by capture radiation arising in the initial layers of the protection. Secondary gamma radiation generated during the passage of a neutron flux through the thickness of the composite does not have a noticeable effect on the value of the functionals of gamma quanta behind the shield. The high efficiency of materials based on titanium hydride shot is shown. Behind the protection of a composite based on titanium hydride shot 1 m thick, the dose rate of fast neutrons is three orders of magnitude lower, and the dose rate of gamma rays is two orders of magnitude less than behind serpentinite concrete. The introduction of boron atoms into the composition of the composite, which has a large neutron absorption cross section in the thermal and suprathermal regions of the spectrum, reduces the effect of accumulation of thermal neutrons and the level of captured gamma radiation, but does not affect the attenuation of fast neutrons. The necessity of using titanium hydride shot on a cement binder is shown, which prevents the formation of voids in the protection structure and the gap of neutrons.