Izvestiya vuzov. Yadernaya Energetika

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

Main Areas of Research for the Refurbished SM-3 Reactor

5/18/2026 2026 - #02 Physics and Technology of Nuclear Reactors

Burukin A.V. Kaplina M.S. Kalinina N.K. Kislyakov V.A. Kornilov D.A. Izhutov A.L. Marikhin N.Yu. Moiseev V.S. Palachev P.S. Petelin A.L. Sazontov S.A. Tarasov V.A.

DOI: https://doi.org/10.26583/npe.2026.2.08

UDC: 621.039.553

This paper discusses the experience gained from employing a refurbished core and reflector in the SM-3 high-flux research reactor for irradiation testing of nuclear materials. The refurbished core as well as various test rigs is also described herein. Irradiation testing of structural materials, core components, absorber materials, and neutron sources is conducted in high-temperature loop channels under natural circulation of water with different chemical compositions. A series of tests with microspherical fuel compacts are being conducted at temperatures that can be achieved in the event of disturbances to the HTGR normal operation. Experimental graphite samples and sealed (glued) graphite compounds, proposed as a structural material for these nuclear reactors, were irradiated to achieve target neutron fluence values. Irradiation tests of graphite samples from large-scale blocks have been conducted. The irradiation testing of graphite proposed for use as a HTGR structural material has begun. Radiation creep and low-cycle fatigue testing, with periodic measurements of sample dimensions, is also underway. Samples of alloys proposed as candidate structural materials for a molten salt reactor were irradiated in the SM-3 reflector to study the effect of neutron irradiation on their mechanical and corrosion properties. The samples were irradiated in a fuel salt based on lithium, sodium and potassium fluorides, with additives of actinide and tellurium fluoride simulators, as well as in helium, and in a molten salt of lithium and beryllium fluorides with the addition of plutonium trifluoride. Work is underway to develop a test facility with natural circulation of fuel salts based on molten lithium, sodium, and potassium fluorides, as well as its supporting systems, for irradiation testing structural materials in the reactor reflector. Irradiation rigs and test facilities are being developed for testing candidate cladding materials for use in the VVER-SKD reactor. The reactor’s neutron trap and beryllium reflector channels generate high-specific-activity radioisotopes for medical application, including transplutonium isotopes such as californium-252. These isotopes are used to produce radiopharmaceuticals for use in nuclear medicine as well as ionizing radiation sources (gamma, alpha, and neutron radiation sources).

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the SM-3 reactor neutron trap refurbishment fuel rod graphite irradiation rig irradiation parameters HTGR research MSR SHELF-M radionuclides transplutonium elements

Link for citing the article: Burukin A.V., Kaplina M.S., Kalinina N.K., Kislyakov V.A., Kornilov D.A., Izhutov A.L., Marikhin N.Yu., Moiseev V.S., Palachev P.S., Petelin A.L., Sazontov S.A., Tarasov V.A. Main Areas of Research for the Refurbished SM-3 Reactor. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 2, pp. 115-134; DOI: https://doi.org/10.26583/npe.2026.2.08 (in Russian).

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