Аннотация
The paper considers a method for evaluating the activity of a steel ampoule after reactor irradiation by the Monte Carlo method. The object of study is a single-wall ampoule made of steel 12Cr18Ni10Ti. This ampoule serves as a protective barrier during reactor tests with experimental devices at the IGR reactor. Forecasting the activity value of the ampoule after the reactor start-up will allow timely planning and organization of work on further safe handling of the ampoule. The results of the neutron-physical calculation of the radiation characteristics of the ampoule, performed in the MCNP program using two methods, are presented.