Methods of determining the efficiency of the system that controls the seal-tightness of fuel-rod cladding and localizes FA with leaky fuel rods in a fast reactor are examined. It is shown that the design procedure has significant limitations. A procedure for numerical modeling of the transport of delayed-neutron precursors was developed to take account of the special features of liquid-metal coolant flow. A special computational module FV-BN was developed within the framework of the FlowVision software package. The computational results obtained for the concentration distribution of delayed-neutron precursors are transferred into the deterministic transport code TORT in order to obtain the spatial-energy distribution of the neutron flux density in a three-dimensional geometry. The procedure was verified on full-scale reactor problems by simulating the flow-through parts of the upper mixing chamber of the fast reactor.
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References
D. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, Department of Nuclear Engineering University of California, Berkeley (1976), pp. 299–300.
S. A. Rogozhkin, S. L. Osipov, I. D. Fadeev, et al., “Numerical modeling of thermohydraulic processes in the upper chamber of a fast reactor,” At. Energ., 115, No. 5, 295–298 (2013).
S. A. Rogozhkin, A. A. Aksenov, S. V. Zhluktov, et al., “Development of a turbulent heat transfer model for liquid-metal sodium coolant and its verification,” Vychisl. Mekh. Sploshn. Sred, 7, No. 3, 306–316 (2014).
S. L. Osipov, S. A. Rogozhkin, A.V. Salyaev, et al., “Application of the FlowVision code for modeling the transport of delayed-neutron precursors in sodium-cooled fast reactors,” in: Sci. Techn. Seminar on Problems of Verification and Application of CFD Codes in Nuclear Power, Nizhnii Novgorod, Sept. 19–20, 2012, pp. 893–901.
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Translated from Atomnaya Énergiya, Vol. 128, No. 4, pp. 226–231, April, 2020.
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Rogozhkin, S.A., Osipov, S.L., Salyaev, A.V. et al. Numerical Modeling of Delayed-Neutron Precursor Transport in a Sodium-Cooled Fast Reactor. At Energy 128, 245–250 (2020). https://doi.org/10.1007/s10512-020-00683-7
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DOI: https://doi.org/10.1007/s10512-020-00683-7