EDN: KSSORV
Authors & Affiliations
Volkova S.N.1, Gritsai A.S.1, 2, Danilov I.G.1, Migrov Yu.A.1, Mitskevich A.V.1, Popov A.O.1, Yarushina A.V.1
1 FSUE “Alexandrov NITI”, Sosnovy Bor, Russia
2 Peter the Great St. Petersburg Polytechnic, Sosnovy Bor, Russia
Volkova S.N.1 – Leading Researcher, Cand. Sci. (Tech.).
Gritsai A.S.1, 2– Head of Department Cand. Sci. (Tech.), Senior Lecturer. Contact: 72, Koporskoye shosse, Sosnovy Bor, Leningrad region, Russia, 188540. Tel.: +7 (813) 696-07-90; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Danilov I.G.1 – Leading Software Engineer.
Migrov Yu.A.1 – Chief Researcher, Dr. Sci. (Tech.).
Mitskevich A.V.1 – Engineer 2d Category.
Popov A.O.1 – Head of Group.
Yarushina A.V.1 – Engineer 2d Category.
Abstract
One of the priority problems for the State Corporation Rosatom is the development of nuclear reactors with liquid metal, including heavy liquid metal, cooling, such as small modular reactors.
For this task, a specialized version of the KORSAR/LMR calculation code was developed and verified, based on the basic version of the KORSAR/V1.1 system calculation code with a water coolant and the subsequent version KORSAR/V3, taking into account the presence of non-condensable gases in the loop. The new version of the calculation code is intended to ensure the calculation of the reactors with lead-bismuth coolant safety by numerically modeling steady states, transient and emergency modes.
The paper describes methods of calculating the cooling circuit thermal hydraulics with the two-fluid approximation. A lead-bismuth eutectic alloy is considered as a liquid phase, and a steam-gas mixture is considered as a vapor phase. This approach allows for simulation of circuit-to-circuit leaks.
The KORSAR/LMR code verification matrix is presented. Examples are given of the code validation against experiments in separate-effect and integral test facilities with liquid metal coolant and results of tests in the KM-1 facility with nuclear heating.
Keywords
KORSAR/LMR computer code, liquid metal coolant, gas-vapor mixture, thermohydraulic model, experimental facilities and stands, KM-1 test facility, computer simulation, verification, validation
Article Text (PDF, in Russian)
References
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UDC 621.039:532.542:004.415
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 4, 4:14
