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)
References
- Ignatiev V.V., Kormilitsyn M.V., Kormilitsyna L.A. et al. Molten-Salt Reactor for Nuclear Fuel Cycle Closure on All Actinides. At Energy, 2019, vol. 125, issue 5, pp. 279–283. DOI: https://doi.org/
10.1007/s10512-019-00481-w.
- Ignat’ev V.V., Feinberg O.S., Smirnov V.P. et al. Analysis of the Fuel-Loop Characteristics of a Molten-Salt Nuclear Reactor with a Cavity Core. At Energy, vol. 126, issue 3, pp. 156–16. DOI: https://doi.org/10.1007/s10512-019-00530-4.
- Laureau A., Belle A., Allibert M., Heuer D., Merle E., Pautz A. Unmoderated molten salt reactors design optimization for power stability. Annals of Nuclear Energy, 2022, vol. 177, no. 8, p. 109265. DOI: 10.1016/j.anucene.2022.109265.
- Gatsa P.V., Ignatiev V.V., Feinberg O.S. Teplogidravlicheskiy analiz ZHSR-szhigatelya transuranovykh elementov [Thermal-hydraulic analysis of the MSR fueled with transuranic elements]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2023, no. 5, pp. 54–64.
- Feinberg O.S., Ignatiev S.V., Kotov Ya.A. et al. Fizicheskiye aspekty utilizatsii otkhodov obogashcheniya regenerirovannogo urana iz otrabotavshego yadernogo topliva reaktorov tipa VVER-1000/1200 v zhidkosolevom yadernom reaktore [Physical aspects of the waste of re-enrichment utilization for recycled uranium from VVER-1000/1200 spent fuel reprocessing in molten salt reactors]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2020, no. 5, pp. 66–71.
- Ignat’ev V.V., Surenkov A.I., Gnidoi I.P. et al. Experimental Investigation of Tellurium Corrosion of Nickel-Molybdenum Alloys in Molten Lithium-, Beryllium-, and Uranium-Fluoride Salts. At Energy, 2016, vol. 120, issue 6, pp. 397–402. DOI: https://doi.org/10.1007/s10512-016-0148-1.
- Novikov V.M., Ignatiev V.V., Fedulov V.I., Cherednikov V.N. Zhidkosolevye YaEU: perspektivy i problemy [Molten Salt Nuclear Power Plants: Prospects and Problems]. Moscow, Energoatomizdat Publ., 1990. 192 p.
- Gatsa P.V., Ignatiev V.V., Fejnberg O.S. Teplogidravlicheskiye kharakteristiki issledovatel'skogo zhidkosolevogo reaktora s aktivnoy zonoy polostnogo tipa [Thermal-Hydraulic Characteristics of the Test Molten Salt Reactor With Cavity-Type Core]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2021, no. 3, pp. 43–52.
- Altahhan M.R., Bhaskar S., Ziyad D., Balestra P., Fiorina C., Hou J., Smith N., Avramova M. Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam. Nuclear Engineering and Design, 2020, vol. 369, p. 110826. DOI: 10.1016/j.nucengdes.2020.110826.
- Gatsa P.V. Zhidkosolevoy yadernyy reaktor s aktivnoy zonoy polostnogo tipa [Molten Salt Reactor with Cavity-type Core]. Patent RF, no. 2787572, 2023.
- Kupriyanov K.S., Kolobovnikov I.P., Luchina K.A. et al. Mul'tifizicheskoye modelirovaniye zhidkosolevykh reaktorov [MultiPhysics Modelling of Molten Salt Reactors]. Materialy konferentsii “Teplofizika reaktorov novogo pokoleniya (Teplofizika-2024)” [Proc. of the Scientific Technical Conference “Thermophysics of New Generation Reactors (Thermophysics-2024)”]. Obninsk, 2024, p. 132.
- Programmnyy kompleks ANSYS [The ANSYS Software Package]. Certification Passport No. 327]. Dated April 18, 2013.
- Kupriyanov K.S., Fejnberg O.S., Ignat'ev V.V. Effektivnaya dolya zapazdyvayushchikh neytronov v reaktore s tsirkuliruyushchim zhidkosolevym toplivom [Effective Fraction of Delayed Neutron in Molten Salt Reactor With Circulating Fuel]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2022, no. 2, pp. 97–106.
UDC 621.039.4
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:7
