Experimental and numerical determination of the rate of mass loss and temperature evolution of the single fuel rod cladding imitator during its melting

Nuclear Engineering and Design - Tập 363 - Trang 110681 - 2020
P.D. Lobanov1,2, V.S. Zhdanov1, E.V. Usov1, A.I. Svetonosov1,2, I.A. Klimonov1
1Nuclear Safety Institute Russian Academy of Science, Bolshaya Tulskaya Street, 52, Moscow 115191, Russia
2Institute of Thermophysics Russian, Siberian Branch, Russian Academy of Science, Novosibirsk, Lavrentieva av., 1, 630090, Russia

Tài liệu tham khảo

McCord, 2016, Analytical solutions to the Stefan problem with internal heat generation, Appl. Therm. Eng., 103, 443, 10.1016/j.applthermaleng.2016.03.122 Chen, 1976, Simple heat conduction model with phase change for reactor fuel pin, Nucl. Eng. Des., 60, 452, 10.13182/NSE76-A26905 Epstein, 1979, The melting of finite slabs in flowing nuclear reactor fuel, Nucl. Eng. Des., 52, 411, 10.1016/0029-5493(79)90030-X An, 2014, Thermal analysis of the melting process in a nuclear fuel rod, Appl. Therm. Eng., 68, 133, 10.1016/j.applthermaleng.2014.04.005 Ishii, 1976, Molten clad motion model for fast reactor loss-of-flow accidents, Nucl. Eng. Des., 60, 435, 10.13182/NSE76-3 Chen, 1977, Parametric study of the molten-clad motion based on one-dimensional model, Nucl. Eng. Des., 41, 1, 10.1016/0029-5493(77)90088-7 Vlasichev, 2001, Numerical simulation of the motion and solidification of melted fuel during serious accident in a fast reactors, Atomic Energy, 90, 357, 10.1023/A:1011316323468 Butov, 2019, The EUCLID/V2 code physical models for calculating fuel rod and core failures in a liquid metal cooled reactor, Therm. Eng., 66, 293, 10.1134/S0040601519050021 Li, 2017, Developed of a sub-channel thermal hydraulic analisis code and its application to lead cooled fast reactor, Appl. Thermal Eng., 117, 443, 10.1016/j.applthermaleng.2017.02.044 Yamano, 2009, A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor, Nucl. Eng. Des., 239, 1673, 10.1016/j.nucengdes.2009.03.010 Wahnon S., Ammirabile L., Kloosterman J., Lathouwers D. Multi-physics models for design basic accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments. Nucl. Eng. Design. v. 331. 2018. pp. 331–341. Kayser, 1998, Summary of the SCARABEE-N subassembly melting and propagation tests with an application to a hypothetical total instantaneous blockage in a reactor, Nucl. Sci. Eng., 128, 144, 10.13182/NSE98-A1950 Ferguson D.R., Cahalan J.E., Deitrich L.W., Bowers C.H., 1979. A Study of the LOCA-2 Termination Potential for the LOF Accident in IMFBR's. In: Proc. Intern. Mtg. on Fast Reactor Safety Technology, Seattle, pp.110–119. Deitrich, L.W., An Assessment of Early Fuel Dispersal in the Hypothetical Loss-of-Flow Accident. In: Proc. of the Int. Meeting on Fast Reactor Safety, Seattle, WA, August 1979, 615-623. Sato, 2004, Transient fuel behavior and failure condition in the CABRI-2 experiments, Nucl. Technol., 145, 115, 10.13182/NT04-A3464 Dickerman C.E., Rothman A.B., Klickman A.E., Spencer, B.W., DeVolpi, A., 1979. Summary of TREAT experiments on oxide core-disruptive accidents ANL-79-13, Reactor Analysis and Safety Division, February. Barts E.W., Deitrich L.W., Eberhart J.G., Fischer A.K., Meek C.C., Summary and evaluation – fuel dynamics loss-of-flow experiments (tests L2, L3, and L4) ANL-75-57, Reactor Analysis and Safety Division, September 1975. Wright, S.A., Worledge, H., Cano, G.L., Mast, P.K., Briscoe, F., Fuel-Disruption Experiments Under High-Ramp-Rate Heating Conditions NUREG/CR- 3862, SAN081-0413, October 1983. Wright, 1985, In-pile observations of fuel and clad relocation during LMBFR Core Disruptive Accidents in the STAR Experiments, Nucl. Technol., 71, 187, 10.13182/NT85-A33719 Vurim A.D., Zhdanov V.S., Zverev V.V., Pivovarov O.S., Kulinich Yu.A., The test results of model fuel rods of the BREST-300 type in the IGR reactor, Vestnik NNC RK, Issue 1, January 2000, pp. 25–30. (in Russian). Usynin, Yu.I., Anoshkin, G.N., Vlasichev, et al. Model study of processes accompanying overheating of fuel elements, Soviet Atomic Energy, v.61, i. 5, 1986, pp. 906–910. Nikolopoulos, 1981, The influence of sodium vapour on the wetting of UO2, -stainless steel 1.4970 (liquid) and its interpretation using scanning auger spectroscopy, J. Nucl. Mater., 101, 277, 10.1016/0022-3115(81)90170-7 Usov, 2018, Fuel pin melting in a fast reactor and melt solidification: simulation using the SAFR/V1 module of the EVKLID/V2 integral code, At. Energ., 124, 147, 10.1007/s10512-018-0389-2 Usov, 2018, SAFR/V1 (EVKLID/V2 Integral Code Module) aided simulation of melt movement along the surface of a fuel element in a fast reactor during a serious accident, At. Energ., 124, 232, 10.1007/s10512-018-0403-8 Usov, 2017, Features of the numerical solution of thermal destruction fuel pins problems in the fast reactor, IOP Conf. Series: J. Phys.: Conf. Series, 891 Usov, 2018, Numerical simulation of melt relocation and heat transfer during severe accidents in the fast reactors, IOP Conf. Series: J. Phys.: Conf. Series, 1105 Alexiades V., Solomon A.D., Mathematical Modeling of Melting and Freezing Processes. Hemisphere Publ. Co. 1993. 323 p. Usov, 2018, Experimental-based verification of the SAFR/V1 module of the EVKLID/V2 integral code for thermal breakdown of fuel pins in fast reactor, Atomic Energy, 124, 287, 10.1007/s10512-018-0412-7 Butov, 2019, Verification of the EUCLID/V2 code based on experiments involving destruction of a liquid metal cooled reactor’s core components, Therm. Eng., 66, 302, 10.1134/S0040601519050033 Alekseenko, 1994, Wave flow of liquid films, Begell., 313 Gimbutis, 1977, Heat transfer in the flow of a liquid-metal film under gravity on a vertical wall, J. Eng. Phys. Thermophys., 32, 115, 10.1007/BF00858492 Thermophysical properties of materials for nuclear engineering: a tutorial and collection of data IAEA. Vienna. 2008. 191 p. Deshpande, 1964, Thermal expansion of tetragonal tin, Acta Cryst., 14, 355, 10.1107/S0365110X61001212 Thermodynamic data for fifty reference elements. NASA technical papers 3287. 1993. 238 p. Assael, 2010, Reference data for the density and viscosity of liquid copper and liquid tin, J. Phys. Chem. Ref. Data, 39, 10.1063/1.3467496