Izvestiya vuzov. Yadernaya Energetika

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

Computational Study into the Experimental Capabilities of the MTIR-SKD Reactor

3/25/2025 2025 - #01 Physics and technology of nuclear reactors

Lapin A.S. Blandinsky V.Y. Nevinitsa V.A. Pustovalov S.B. Sedov A.A. Subbotin S.A. Fomichenko P.A.

DOI: https://doi.org/10.26583/npe.2025.1.01

Two stages of the MTIR-SKD reactor operation are planned: a test stage and a research stage. This paper considers the research stage of the MTIR-SKD experimental reactor operation, the purpose of which is to investigate current and advanced light-water reactors. The MTIR-SKD driver-type core provides a fast neutron spectrum with the possibility for the local warmup in ampoule devices and independent loop channels. Irradiation channels will be installed in the core center and periphery, as well as instead of the reactor’s changeable reflector cartridges. The MTIR-SKD irradiation channels and independent loops will provide ample opportunities both for undertaking a research on effects from neutron irradiation of different materials, and for testing a variety of fuel assembly designs and operating conditions (temperature, pressure, neutron spectrum), as well as for investigating transient and emergency processes. The MTIR-SKD channels can be used to irradiate different types of fuel, and structural and absorbing materials with different coolant inlet temperatures (from 250 to 450°C) and, consequently, its inlet density (from 800 to 100 kg/m3 respectively), providing different neutron spectrum options for the experimental fuel assembly in a range from thermal to fast spectrum. The MTIR-SKD allows experiments to increase power and simulate emergency processes, including reactivity accidents (RIA). The strong primary and safeguard vessels of the independent loop channels also make it possible to simulate loss-of-pressure emergencies of the LB LOCA and SB LOCA types. The peripheral independent loop channel will allow undertaking experiments for simulation of alternative reactor concepts with reactors with SKD coolant parameters, such as a single-circuit concept with the pseudophase transition in the core (VVER-SKD-1700), and with natural coolant circulation in the core (SKDI). In addition, the peripheral channel allows accelerated irradiation of fuel rods used in current VVER reactors, taking into account the reproduction of the ratio between damage dose rates and burnup.

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VVER-SKD MTIR-SKD light water reactor supercritical coolant parameters test reactor research reactor

Link for citing the article: Lapin A.S., Blandinsky V.Y., Nevinitsa V.A., Pustovalov S.B., Sedov A.A., Subbotin S.A., Fomichenko P.A. Computational Study into the Experimental Capabilities of the MTIR-SKD Reactor. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 1, pp. 7-23; DOI: https://doi.org/10.26583/npe.2025.1.01 (in Russian).

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