Abstract
The BOR-60 reactor is actively used for conducting irradiation experiments in support of nuclear reactors both under operation, construction and design. Most of these experiments are conducted in the reactor core using various types of irradiation rigs. However, in recent years there has been keen interest in conducting reactor tests in the BOR-60 blanket. This is associated with several factors: the availability of blanket cells, weak influence on the reactor neutronic characteristics and safety, wide range of irradiation conditions (temperature, neutron flux density, damage doses, neutron spectrum), and cost of irradiation. The experience in BOR-60 blanket computational and experimental studies showed an ill agree-ment between the calculated and experimental neutronic characteristics. In addition to no orientation of the samples under study relative to the core center, there is a significant radial non-uniformity in the neutronic characteristics distribution in the BOR-60 blanket that limits its application for experimental studies. Therefore, detailed computational and experimental studies of the spatial-energy distribution of neutrons in the BOR-60 steel blanket is an important and urgent task.
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