Thermohydraulic validation is a priority for the ZhSR-S [MOSART] molten-salt nuclear transmuter for transuranium elements from the spent nuclear fuel of solid-fuel thermal reactors. In the present article, the results of coupled neutronics and thermohydraulics calculations, based on which the configuration of the cavity core and fuel loop were chosen, are generalized. The thermohydraulic validation of such a reactor was preceded by the development of an experimental database on the physical properties of the fuel salt with the molar composition 73LiF–27BeF2 + AnF3 and 58NaF–15LiF–27BeF2 + AnF3. The optimized 2400 MW(t) ZhSr-S core satisfies the two most important requirements of thermohydraulics: no recirculation or stagnant zones and quite low maximum temperature of the solid reflectors so that they can be used for a long time.
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References
V. V. Ignat’ev, O. S. Feinberg, A. V. Zagnitko, et al., “Molten salt reactors: new possibilities, problems, and solutions,” At. Energ., 112, No. 3, 157–165 (2012).
O. Feynberg, V. Ignatiev, A. Surenkov, et al., “Advanced reactor technology options for utilization and transmutation of actinides in spent nuclear fuel: molten salt reactor with fertile free fuel,” in: IAEA TECDOC-1626, IAEA, Vienna (2009), pp. 128–168.
V. M. Novikov, V. V. Ignat’ev, V. I. Fedulov, and V. N. Cherednikov, Molten-Salt NPF: Prospects and Problems, Energoatomizdat, Moscow (1990).
V. Khokhlov, V. Ignatiev, and V. Afonichkin, “Evaluating physical properties of molten salt reactor fluoride mixtures,” J. Fluor. Chem., 130, 30–37 (2009).
FlowVision: System for Modeling the Motion of Fluids and Gases, Ver. 2.5, TESIS, Moscow (1999–2008).
C. Chang and Chin Pan, “Numerical simulation for the design of MOSART flow distributor,” in: Rus. Sci. Sym. on Nuclear Research and Medical Application, NTHU, Taiwan, Jan. 11, 2011, pp. 95–106.
V. Tuyen and H. Rouch, “Thermal-hydraulic simulations: two core shape comparison and inlet diameter effects,” in: FP6 EVOL Project Workshop: WP2 Design and Safety, Grenoble, France, March 6–7, 2012, pp. 163–184.
Program Plan for Development of Molten Salt Breeder Reactors, Rep. ORNL-5018 (1974).
V. Ignatiev, O. Feynberg, V. Afonichkin, et al., “Molten salt actinide recycler & transforming system without and with Th–U support: fuel cycle flexibility and key material properties,” Ann. Nucl. Energy, 64, 408– 420 (2014).
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Translated from Atomnaya Énergiya, Vol. 126, No. 3, pp. 137–143, March, 2910.
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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 126, 156–162 (2019). https://doi.org/10.1007/s10512-019-00530-4
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DOI: https://doi.org/10.1007/s10512-019-00530-4