Abstract—
The article presents the results of new investigations into possible loss of cooling of spent fuel assemblies (FAs) stored in near-reactor spent fuel pools of BWR and VVER reactor plants (RPs). The experiments were carried out in 2022 on the ALADIN installation (Germany, a BWR type RP) and the “Reflooding test bench” installation (Russia, a VVER type RP). In comparing the experimental data obtained on different test benches, it was noted that the thermal-hydraulic processes that were observed during water boiling, cooling, and subsequent heat-up of fuel assemblies had similar patterns for the above-mentioned reactor types. By using the KORSAR/GP computer code, posttest calculations of experiments were carried out, the results of which were compared with the basic experimental data on the maximum fuel rod temperature and water level. Good agreement between the calculated and experimental results was obtained. Deviations of the calculated data from the experimental results were estimated with respect to the water boiling onset and fuel rod heat-up onset moments, the moment at which the fuel rod temperature reaches its maximum value, and its absolute values. The obtained results can be used for validating thermal-hydraulic codes, substantiating their applicability, and for performing safety analysis under the conditions of accidents involving loss of spent fuel pool cooling at NPPs with VVER/PWR reactor plants.
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REFERENCES
D. Wang, I. C. Gauld, G. L. Yoder, L. J. Ott, G. F. Flanagan, M. W. Francis, E. L. Popov, J. J. Carbajo, P. K. Jain, J. C. Wagner, and J. C. Gehin, “Study of Fukushima Daichi nuclear power station unit 4 spent fuel pool,” Nucl. Technol. 180, 205–215 (2017). https://doi.org/10.13182/NT12-A14634
O. Coindreau, B. Jäckel, F. Rocchi, F. Alcaro, D. Angelova, G. Bandini, M. Barnak, M. Behler, D. F. da Cruz, R. Dagan, P. Drai, S. Ederli, L. E. Herranz, T. Hollands, G. Horvath, et al., “Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool,” Ann. Nucl. Energy 120, 880–887 (2018). https://doi.org/10.1016/j.anucene.2018.06.043
R. M. Sledkov and O. E. Stepanov, “Cross-verification of the ROK2 program on the problem with loss of cooling of the spent fuel pool of the VVER-1000 reactor facility,” Vopr. At. Nauki Tekh., Ser. Fiz. Yad. Reaktorov, No. 1, 32–36 (2017).
S. R. Chen, W. C. Linc, Y. M. Ferng, C. C. Chieng, and B. S. Pei, “Development of 3-D CFD methodology to investigate the transient thermal-hydraulic characteristics of coolant in a spent fuel pool,” Nucl. Eng. Des. 275, 272–280 (2014). https://doi.org/10.1016/j.nucengdes.2014.05.020
M. M. Bedretdinov, V. E. Karnaukhov, and O. E. Stepanov, “Cross-verification of the KORSAR/GP code and CFD-code for conditions of a two-section near-reactor spent fuel pool,” Vopr. At. Nauki Tekh., Ser. Fiz. Yad. Reaktorov, No. 2, 32–36 (2021).
Phenomena Identification and Ranking Table (PIRT) on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions, WGFS Report No. 7443, NEA/CSNI/R(2017)18, (OECD Nuclear Safety and Regulation, 2017).
S. G. Durbin, E. R. Lindgren, A. S. Goldmann, M. Zavisca, Z. Yuan, R. Karimi, A. Krall, and M. Khatib-Rahbar, Spent Fuel Pool Project Phase I: Pre-Ignition and Ignition Testing of a Single Commercial 17 × 17 Pressurized Water Reactor Spent Fuel Assembly under Complete Loss of Coolant Accident Conditions, NUREG/CR-7215 (U.S. Nuclear Regulatory Commission, 2016).
B. Migot, G. Brilliant, J. Martin, and S. Morin, “Denopi project devoted to spent fuel pool accidents: Overview on the thermal hydraulics experimental facilities,” in Proc. 19th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, Mar. 6–10, 2022 (American Nuclear Society, 2022).
M. Arlit, C. Partmann, E. Schleicher, C. Schuster, A. Hurtado, and U. Hampel, “Instrumentation for experiments on a fuel element mock-up for the study of thermal hydraulics for loss of cooling or coolant scenarios in spent fuel pools,” Nucl. Eng. Des. 336, 105–111 (2018). https://doi.org/10.1016/j.nucengdes.2017.06.034
C. Partmann, C. Schuster, and A. Hurtado, “Experimental investigation of the thermal hydraulics of a spent fuel pool under loss of active heat removal conditions,” Nucl. Eng. Des. 330, 480–487 (2018). https://doi.org/10.1016/j.nucengdes.2018.02.023
D. N. Moisin and O. E. Stepanov, “Post-test calculations of experiments for conditions of cooling loss of the spent nuclear fuel pool using the KORSAR/GP code,” in Proc. 22nd Int. Conf. of Young Specialists on Nuclear Power Facilities, Podolsk, Russia, Apr. 12–13, 2023 (Gidropress, Podolsk, 2023).
M. M. Bedretdinov, O. E. Stepanov, R. M. Sledkov, and C. Schuster, “KORSAR/GP and SOCRAT/V1 codes’ validation for the loss of cooling at spent fuel pool conditions,” Nucl. Eng. Des. 375, 213–226 (2021). https://doi.org/10.55176/2414-1038-2021-3-213-226
V. E. Karnaukhov, M. M. Bedretdinov, P. S. Gagulin, R. M. Sledkov, and O. E. Stepanov, “Analysis of the sensitivity and uncertainty of calculation using the KORSAR/GP code for accidents with a failure of storage pools’ cooling system,” Therm. Eng. 70, 339–345 (2023). https://doi.org/10.1134/S0040601523050026
P. Zedler, C. Schuster, W. Lippmann, and A. Hurtado, “Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools,” Exp. Comput. Multiphase Flow 2, 13–21 (2020). https://doi.org/10.1007/s42757-022-0132-z
R. Oertel, T. Hanisch, E. Krepper, D. Lucas, F. Rüdiger, and J. Fröhlich, “Two-scale CFD analysis of a spent fuel pool involving partially uncovered fuel storage racks,” Nucl. Eng. Des. 341, 432–450 (2019). https://doi.org/10.1016/j.nucengdes.2018.10.014
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Ivanova, N.V., Bedretdinov, M.M., Stepanov, O.E. et al. Posttest Calculations of Thermal-Hydraulic Conditions for Test Benches Simulating a Loss of Spent Fuel Pool Cooling Accident at BWR and VVER-1000/1200 Reactors. Therm. Eng. 71, 412–423 (2024). https://doi.org/10.1134/S0040601524050069
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DOI: https://doi.org/10.1134/S0040601524050069