Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Experience of Using BN-600 Reactor Core for Experimental Irradiation

9/10/2025 2025 - #03 Nuclear materials

Belov S.B. Vasilyev B.A. Radionycheva A.A. Farakshin M.R. Tuchkov A.M.

DOI: https://doi.org/10.26583/npe.2025.3.10

UDC: 621.039.534.23:621.039.526

The article is dedicated to the accumulated experience of using the core of an operating fast neutron reactor BN-600 for the purposes of experimental irradiation, which was carried out in many directions. The information on different types of experimental subassemblies (SAs) is provided.

In order to increase the burnup of uranium fuel, work was constantly underway to develop new types of structural materials for fuel cladding and fuel SA wrapper tube. This made it possible to carry out three modernization of the core and to plan a further increase in the fuel lifetime. Within the material test SAs, irradiation of test samples of 12% chromium, FM and ODS steels was provided. Reactor tests and material studies were carried out as part of work to extend the life of the reactor to 60 years.

A large volume of amount reactor tests was carried out in order to justify the performance of various types of mixed oxide uranium-plutonium fuel – pelleted and vibrocompacted. To date, the results of experimental irradiation of a new type of fuel – mixed nitride uranium-plutonium within experimental SAs have been obtained. There is significant experience of irradiation in the reactor of experimental irradiation devices for the production radioisotopes for industrial (60Co) and scientific (37Ar) purposes, as well as experimental CPS absorbers rods with new design solutions and materials.

When organizing reactor tests of experimental SAs, the main approaches were used when placing them in the core. Particular attention was paid to the analysis of their impact on the safety of the reactor and the operating parameters of standard SAs.

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BN-600 core reactor tests structural materials experimental assembly material test SA mixed oxide uranium-plutonium (MOX) fuel mixed nitride uranium-plutonium (MNUP) fuel BN-800 BN-1200 BREST irradiation assembly irradiation parameters radioisotopes production CPS absorber rods

Link for citing the article: Belov S.B., Vasilyev B.A., Radionycheva A.A., Farakshin M.R., Tuchkov A.M. Experience of Using BN-600 Reactor Core for Experimental Irradiation. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 3, pp. 133-152; DOI: https://doi.org/10.26583/npe.2025.3.10 (in Russian).

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