CALCULATION OF THE ACTIVITY OF A STEEL AMPOULE AFTER REACTOR IRRADIATION

A. S. Surayev, G. G. Kakimova, Р. А. Иркимбеков

2023

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DOI 10.52676/1729-7885-2023-4-85-90
Data confidence 70 medium
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Abstract

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.