Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench

References

• R. V. ARUTYUNYAN, “Chinese Syndrome,” Nature, 11, 35 (1990).
   Google Scholar
• Y. S. VASILIEV et al., “Experimental Studies Carried Out in IAE on Simulation of Process Typical for Reactor Severe Accidents,” Bulletin of NNC RK, 4, 26 (2009) ( in Russian).
   Google Scholar
• C. JOURNEAU, “Contribution of Tests on Prototypical Materials on the PLINIUS Platform to the Study of Severe Accidents in Nuclear Reactors,” University of Orleans (2008) ( in French).
   Google Scholar
• V. A. SIDORENKO, “Issues of Safe Operation of WWER Reactors,” Atomizdat, (1977) ( in Russian).
   Google Scholar
• T. K. MARGULOVA, Nuclear Power Stations, Higher School (1994) ( in Russian).
   Google Scholar
• J. M. BROUGHTON et al., “A Scenario of the Three Mile Island Unit 2 Accident,” Nucl. Technol., 87, 1, 34 (1989); https://doi.org/10.13182/NT89-A27637.
   Google Scholar
• S. A. ANDRUSHECHKO et al., NPP with a WWER-1000 Reactor. From the Physical Foundations of Operation to the Evolution of the Project, Logos (2010) ( in Russian).
   Google Scholar
• C. JOURNEAU et al., “Contributions of the VULCANO Experimental Programme to the Understanding of MCCI Phenomena,” Nucl. Eng. Technol., 44, 3, 261 (2012); https://doi.org/10.5516/NET.03.2012.703.
   Web of Science ®Google Scholar
• J. SONG et al., “A Use of Prototypic Material for the Investigation of Severe Accident Progression,” Prog. Nucl. Energy, 93, 297 (2016); https://doi.org/10.1016/j.pnucene.2016.09.003.
   Web of Science ®Google Scholar
• J. J. FOIT et al., “Experiments on MCCI with Oxide and Steel,” Ann. Nucl. Energy, 74, 100 (2014); https://doi.org/10.1016/j.anucene.2014.06.025.
   Web of Science ®Google Scholar
• N. A. NAZARBAYEV et al., Scientific, Technical and Engineering Work to Ensure the Safety of the Former Semipalatinsk Test Site, Vol. 3, Worldwide Promedia, London (2017).
   Google Scholar
• M. K. SKAKOV et al., “National Nuclear Center of the Republic of Kazakhstan, Assignee. Induction Furnace for Melting High Temperature Materials. Patent of the Republic of Kazakhstan for Utility Model No. 3038” (Aug. 20, 2018).
   Google Scholar
• A. VURIM et al., “Information and Analytical System for Processing of Research Results to Justify the Safety of Atomic Energy,” Appl. Sci., 12, 9705 (2022); https://doi.org/10.3390/app12199705.
   Google Scholar
• N. MUKHAMEDOV et al., “Thermal Properties of Prototype Corium of Fast Reactor,” Nucl. Eng. Des., 322, 27 (2017); https://doi.org/10.1016/j.nucengdes.2017.06.026.
   Web of Science ®Google Scholar
• N. Y. MUKHAMEDOV et al., “Microstructure and Mechanical Properties of the LWR Solidified Melt Prototype Obtained by the Out-of-Pile Experiment,” Ann. Nucl. Energy, 163, 108594 (2021); https://doi.org/10.1016/j.anucene.2021.108594.
   Web of Science ®Google Scholar
• N. Y. MUKHAMEDOV, Y. A. KOZHAKHMETOV, and V. K. TSKHE, “Microstructure and Mechanical Properties of the Solidified Melt Obtained by the In-Pile Test,” Ann. Nucl. Energy, 179, 109404 (2022); https://doi.org/10.1016/j.anucene.2022.109404.
   Web of Science ®Google Scholar
• Y. PONKRATOV et al., “Methodology of Corrosion Testing of Nuclear and Fusion Reactors Materials Using TGA/DSC and MS Complex Techniques,” Eurasian Chem.-Technol. J., 21, 1, 35 (2019); https://doi.org/10.18321/ectj787.
   Web of Science ®Google Scholar
• Y. PONKRATOV et al., “Methodology of the Experiments to Study Lithium CPS Interaction with Deuterium Under Conditions of Reactor Irradiation,” Eurasian Chem.-Technol. J., 21, 2, 107 (2019); https://doi.org/10.18321/ectj820.
   Web of Science ®Google Scholar
• I. TAZHIBAYEVA et al., “Study of Liquid Tin-Lithium Alloy Interaction with Structural Materials of Fusion Reactor at High Temperatures,” Nucl. Mater. Energy, 30, 101152 (2022); https://doi.org/10.1016/j.nme.2022.101152.
   Web of Science ®Google Scholar
• M. SKAKOV et al., “Effect of a High-Temperature Treatment on Structural-Phase State and Mechanical Properties of IMC of the Ti-25Al-25Nb at. % System,” Materials, 15, 16, 5560 (2022); https://doi.org/10.3390/ma15165560.
   PubMed Web of Science ®Google Scholar
• “Test and Evaluation Plan for Passive Debris Cooling System,” T. KURITA et al., Eds., Proc. 9th Int. Conf. Nuclear and Radiation Physics (ICNRP), p. 19, Almaty, Kazakhstan, September 24–27, 2013.
   Google Scholar
• “Characterization of Fuel Debris by Large-Scale Simulated Debris Examination for Fukushima Daiichi Nuclear Power Station,” S. KAWANO et al., Eds. Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP), p. 1105, Fukui and Kyoto, Japan, April 24–28, 2017.
   Google Scholar
• “Results of LHI Tests and Associated Analyses on In-Vessel Debris Coolability,” Y. MARUYAMA et al., Eds., Proc. 3d Korea-Japan Symp. on Nuclear Thermal Hydraulics and Safety (NTHAS), Kyeongju, Korea, October 13–16, 2002.
   Google Scholar
• Y. MARUYAMA et al., “Study on Concrete Degradation During Molten Core/Concrete Interactions,” Nucl. Eng. Des., 236, 19–21, 2237 (2006); https://doi.org/10.1016/j.nucengdes.2006.03.055.
   Web of Science ®Google Scholar
• V. V. BAKLANOV, V. S. ZHDANOV, and E. V. MALYSHEVA, “Experimental Study of Processes During the Retention of the Corium Melt in the Reactor Vessel (INVECOR),” Bulletin of NNC RK, 1, 55 (2009) ( in Russian).
   Google Scholar
• M. K. BEKMULDIN et al., “Heat-Resistant Composite Coating with a Fluidized Bed of the Under-Reactor Melt Trap of a Light-Water Nuclear Reactor,” Eurasian Phys. Tech. J., 18, 3, 65 (2021); https://doi.org/10.31489/2021No3/65-70.
   Google Scholar
• M. SKAKOV et al., “The Method of Corium Cooling in a Core Catcher of a Light-Water Nuclear Reactor,” Eurasian Phys. Tech. J., 19, 69 (2022); https://doi.org/10.31489/2022No3/69-77.
   Google Scholar
• M. SKAKOV et al., “On the Possibility of Forming a Corium Pool by Induction Heating in a Melt Trap of the Lava-B Facility,” Appl. Sci., 13, 2480 (2023); https://doi.org/10.3390/app13042480.
   Google Scholar
• K. O. TOLEUBEKOV, A. S. AKAEV, and M. K. BEKMULDIN, “Improving the Efficiency of the Induction Heating System for Imitation the Residual Energy Release in the Corium During the Interaction with Heat-Resistant Materials,” Bulletin of NNC RK. 4, 47 (2020) (in Russian).
   Google Scholar
• K. O. TOLEUBEKOV, A. S. KHAZHIDINOV, and A. S. AKAEV, “Modeling of the Induction Heating for Imitation Decay Heat in the Corium During the Interaction with Heat-Resistant Materials,” Bulletin of NNC RK., 1, 9 (2021); https://doi.org/10.52676/1729-7885-2021-1-9-14 ( in Russian).
   Google Scholar
• Rotating Electrical Machines. Methods for Determining Losses and Efficiency, Standard No. 25941-83, Euro-Asian Council for Standardization, Metrology and Certification, Publishing House of Standards, Moscow (2003) (in Russian).
   Google Scholar
• V. S. CHIRKIN, Thermophysical Properties of Nuclear Engineering Materials, Atomizdat (1968) (in Russian).
   Google Scholar