EDN: PCUFLC
Authors & Affiliations
Gatsa P.V., Ignatiev V.V., Kupriyanov K.S.
National Research Centre “Kurchatov Institute”, Moscow, Russia
Gatsa P.V. – Junior Researcher. Contacts: 1, pl. Akademika Kurchatova, Moscow, Russia, 123182. Tel.: +7 (915) 198-80-33; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it., This email address is being protected from spambots. You need JavaScript enabled to view it..
Ignatiev V.V. – Head of Department of Molten Salt Nuclear Reactors, Dr. Sci. (Tech.).
Kupriyanov K.S. – Laboratory Research Assistant.
Abstract
Nuclear power has a number of advantages, including environmental friendliness, high power, etc., but it also has problems, such as waste disposal from irradiated nuclear fuel. A molten salt nuclear reactor (MSR) can help solve this problem by reducing the amount of high-level waste. The Kurchatov Institute has proposed the design of a MOSART for burning transuranic elements (minor actinides) with a cyclone-type core. Thermal-hydraulic and neutron-physical processes in MSR are closely related and jointly determine the reactor operation, therefore modelling should be carried out taking into account their mutual influence. In this paper, a multiphysics analysis of the cyclone MOSART is performed. The results of the multiphysics calculation show smaller deviations from the average parameters compared to the previously performed thermal-hydraulic calculation: no more than 4 % for fuel salt heating and no more than 1.1 % for the mass flow rate through each core exit. The correction factors for 6 groups of delayed neutrons and the overall correction factor (reduction of βeff relative to a reactor with fixed fuel) were calculated. The results showed that the relative reduction of βeff is 13 %, and the effective fraction of delayed neutrons is 0.00265.
Keywords
core, molten salt reactor, multi-physics calculation, neutron-physical characteristics, reactor circuit, thermal-hydraulic characteristics, fuel salt, lithium and beryllium fluorides, cyclonic flow, circulating fuel
Article Text (PDF, in Russian)
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UDC 621.039.4
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:7
