Abstract
The paper presents experimental studies of the attenuation of neutron and photon radiation of a nuclear reactor by a radiation-protective metal hydride composite, as well as the distribution of dose and spatial-energy characteristics of primary and secondary gamma radiation in the material. It is shown that the formation of the gamma radiation dose rate behind the protection is due to the capture gamma quanta formed in the initial layer of the material. Based on the results of the reactor protective properties of the material, the verification of the computational model of the experiment in two-dimensional geometry by the method of discrete ordinates according to the DORT program was carried out. The deviations between the calculated and experimental values of the relaxation lengths for fast neutrons were no more than 5 %, for gamma radiation no more than 7 %, which confirms the validity of the calculation methods used and the possibility of using the data obtained with a high degree of reliability when designing the geometry of the radiation protection of a reactor made of metal hydride composite
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