Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor
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The results of verification of the IBRAE-developed SAFR/V1 module, describing in the EVKLID/V2 integral code the thermal breakdown of fuel pins, on the basis of data obtained using experimental facilities. The experiments performed on the TREAT and DEH facilities at the Argonne National Laboratory and on a bench at the Nizhny Novgorod State Technical University were picked for the verification process. The computational error was evaluated for individual parameters on the basis of the verification results. The impact of the uncertainties in the initial data on the computational results was analyzed.
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- 1.V. M. Alipchenkov, V. V. Belikov, and V. N. Vasekin, “Verifi cation of the integral universal settlement code EVKLID/V1 for the installations BREST-OD-300 and BN-1200,” in: Innovative Projects and Technologies of Nuclear Power, Moscow, Oct. 7–10, 2014, Vol. 2, pp. 175–191.Google Scholar
- 2.B. Spencer, Final Report on TREAT Tests R4 and R5; Seven-Pin, Loss-of-Flow Tests with Full-Length, Unirradiated FFTF-Type Fuel Pins, ANL (1979).Google Scholar
- 3.R. Holtz, Final Report on TREAT Test R3 and R5; A Single-Pin Loss-of-Flow Experiment, ANL (1977).Google Scholar
- 4.L. Deitrich, “Experiments on transient fuel failure mechanisms,” in: Presentation at the Intern. Working Group on Fast Reactors Specialists Meeting on Fuel Failure Mechanisms, Washington, May 11, 1975.Google Scholar
- 5.B. Wrona, T. Galvin, and D. Stahl, “Out-of-reactor experimental study of fuel-pin failure phenomena,” in: Meeting on Fast Reactor Safety and Related Physics, Chicago, Oct. 6, 1976, pp. 1–12.Google Scholar
- 6.G. B. Usynin, Yu. I. Anoshkin, and M. A. Semenychev, “Investigation of the melting of fuel elements on simulators with fuel compositions,” At. Energ., 70, No. 2, 108–110 (1991).Google Scholar
- 8.G. N. Vlasichev, “Computational analysis of experiments on the destruction of electrically heated simulators of the fuel elements of nuclear reactors,” Izv. Vyssh. Uchebn. Zaved. Yad. Energet., No. 4, 28–37(2000).Google Scholar
- 9.A. A. Kalashnikova and E. V. Usov, “Development of a software module for calculating the melting of fuel rods and movement of melt in fast reactors at the stage of a severe accident,” in: 3rd Russ. Youth Conf. on Energy, Electromechanics, and Energy-Effi cient Technologies Through the Eyes of Youth, SCAN LLC, Tomsk (2015), pp. 135–138.Google Scholar
- 11.E. V. Usov, A. A. Butov, V. I. Chukhno, et al., “Modeling of the movement of melt along the surface of a fuel rod in a fast reactor fuel rod during severe accident: SAFR/V1 module of the EVCLID/V2 integrated code,” At. Energ., No. 4, pp. 197–201.Google Scholar
- 12.V. M. Alipchenkov, A. M. Anfi mov, D. A. Afremov, et al., “Basic provisions, current state of development, and prospects for further development of next-generation hydraulic thermal computational code HYDRAIBRAE/LM for simulation of fast reactors,” Teploenergetika, No. 2, 54–64 (2016).Google Scholar
- 13.E. V. Usov, A. A. Butov, G. A. Dugarov, et al., “The system of closing relations of the two-fl uid model of the HYDRA-IBRAE/LM/V1 code for the calculation of processes during boiling of sodium in energy equipment channels,” Teploenergetika, No. 7, 48–55 (2017).Google Scholar