Research article

Results of experimental simulation of interaction between corium of a nuclear reactor and sacrificial material (Al2O3) with a lead layer

  • Received: 26 October 2023 Revised: 30 November 2023 Accepted: 19 December 2023 Published: 02 January 2024
  • This paper presents the results of an experimental study of the interaction of a candidate sacrificial material (SM) for a light water reactor melt trap with corium at the Lava-B test-bench. The candidate sacrificial material is a combination of aluminum oxide and a lead layer. The idea of using such a combination of SM is based on the fact that when the lead layer interacts with corium, there will be an increase in the intensity of heat removal from the corium, as well as the chemical interaction between the corium and SM due to the high heat-conducting properties of lead. This approach will improve the efficiency of corium localization in the melt trap compared to the current set of sacrificial material. Experiments have shown active melting and boiling of lead during its interaction with corium. This is confirmed both by the readings of thermocouples and by the X-ray diffraction phase analysis of the deposit material formed on the walls of the melt receiver (MR) of the Lava-B bench, sampled after the experiment. The experiment results show that the lead layer reduces the rate of increase in the temperature of the corium and increases the rate of erosion of the ceramic part of the SM. With these circumstances, it is possible to conclude that the use of aluminum oxide with a lead layer is promising in practice.

    Citation: Mazhyn Skakov, Viktor Baklanov, Maxat Bekmuldin, Ivan Kukushkin, Assan Akaev, Alexander Gradoboev, Olga Stepanova. Results of experimental simulation of interaction between corium of a nuclear reactor and sacrificial material (Al2O3) with a lead layer[J]. AIMS Materials Science, 2024, 11(1): 81-93. doi: 10.3934/matersci.2024004

    Related Papers:

  • This paper presents the results of an experimental study of the interaction of a candidate sacrificial material (SM) for a light water reactor melt trap with corium at the Lava-B test-bench. The candidate sacrificial material is a combination of aluminum oxide and a lead layer. The idea of using such a combination of SM is based on the fact that when the lead layer interacts with corium, there will be an increase in the intensity of heat removal from the corium, as well as the chemical interaction between the corium and SM due to the high heat-conducting properties of lead. This approach will improve the efficiency of corium localization in the melt trap compared to the current set of sacrificial material. Experiments have shown active melting and boiling of lead during its interaction with corium. This is confirmed both by the readings of thermocouples and by the X-ray diffraction phase analysis of the deposit material formed on the walls of the melt receiver (MR) of the Lava-B bench, sampled after the experiment. The experiment results show that the lead layer reduces the rate of increase in the temperature of the corium and increases the rate of erosion of the ceramic part of the SM. With these circumstances, it is possible to conclude that the use of aluminum oxide with a lead layer is promising in practice.



    加载中


    [1] Harutyunyan R (1990) Chinese syndrome. Nature 11: 35–41.
    [2] Fischer M, Bechta S, Bezlepkin V, et al. (2017) Core melt stabilization concepts for existing and future LWRs and associated research and development needs. Nucl Technol 196: 524–537. https://doi.org/10.13182/NT16-19 doi: 10.13182/NT16-19
    [3] Khabensky V, Granovskii V, Bechta S (2009) Severe accident management concept of the VVER-1000 and the justification of corium retention in a crucible-type core catcher. Nucl Eng Technol 41: 561–574. https://doi.org/10.5516/NET.2009.41.5.561 doi: 10.5516/NET.2009.41.5.561
    [4] Song J, Suh N (2009) An evolution of molten core cooling strategies. Nucl Eng Des 239: 1338–1344. https://doi.org/10.1016/j.nucengdes.2009.02.010 doi: 10.1016/j.nucengdes.2009.02.010
    [5] Fish J, Piltch M, Arellano F (1982) Demonstration of passively-cooled particle-bed core retention. Proceedings of the LMFBR Safety Topical Meeting, Lyon, France, 327–336.
    [6] Turrichia A (1992) How to avoid molten core/concrete interaction (and steam explosions). Proceedings of 2nd OECD(NEA)CSNI Specialists Meeting of Molten Debris-Concrete Interaction, Karlsruhe, 503.
    [7] Fieg G, Möschke М, Werle H (1995) Studies for staggered pans core catcher. Nucl Technol 111: 331–340. https://doi.org/10.13182/NT95-A15863 doi: 10.13182/NT95-A15863
    [8] Tromm W, Alsmeyer H (1995) Experiments for a core catcher concept based on water addition from below. Nucl Eng Des 157: 437–445. https://doi.org/10.1016/0029-5493(95)01000-8 doi: 10.1016/0029-5493(95)01000-8
    [9] Fischer M (2004) The severe accident mitigation concept and the design measures for core melt retention of the European pressurized reactor (EPR). Nucl Eng Des 230: 169–180. https://doi.org/10.1016/j.nucengdes.2003.11.034 doi: 10.1016/j.nucengdes.2003.11.034
    [10] Hamazaki R, Nakagawa T, Katagiri N, et al. (2011) Evaluation on core melt retention in core catcher of Toshiba's EU-ABWR. Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP), Nice, France, 11414.
    [11] Lee J, Kim J, Kim T, et al. (2017) Overview of ex-vessel cooling strategies and perspectives. Proceedings of Transactions of the Korean Nuclear Society Spring Meeting Jeju, Korea, 1–5.
    [12] Song K, Nguyen T, Ha K, et al. (2017) Experimental study on two-phase flow natural circulation in a core catcher cooling channel for EU-APR1400 using air-water system. Nucl Eng Des 316: 75–88. https://doi.org/10.1016/j.nucengdes.2017.03.009 doi: 10.1016/j.nucengdes.2017.03.009
    [13] Kukhtevich I, Bezlepkin V, Granovskii V, et al. (2001) The concept of localization of the corium melt in the ex-vessel stage of a severe accident at a nuclear power station with a VVER-1000 reactor. Therm Eng 48: 699–706.
    [14] Gusarov V, Almyashev V, Beshta S, et al. (2001) Sacrificial materials for safety systems of nuclear power stations: A new class of functional materials. Therm Eng 48: 721–724.
    [15] Stolyarevsky A (2014) The problem of retaining molten fuel in the containment NPPs with WWER. ISJAEE 6: 25–35. Available from: https://www.isjaee.com/jour/article/view/437?locale = en_US.
    [16] Asmolov V, Bechta S, Berkovich V, et al. (2005) Crucible-type core catcher for VVER-1000 reactor. Proceedings of the American Nuclear Society-International Congress on Advances in Nuclear Power Plants, 1221–1227.
    [17] Asmolov V, Zagryazkin V, Isaev I, et al. (2002) Choice of buffer material for the containment trap for VVÉR-1000 core melt. At Energy 92: 5–14. https://doi.org/10.1023/A:1015094327731 doi: 10.1023/A:1015094327731
    [18] Song J, Kim H, Hong S, et al. (2016) A use of prototypic material for the investigation of severe accident progression. Prog Nucl Energ 93: 297–305. https://doi.org/10.1016/j.pnucene.2016.09.003 doi: 10.1016/j.pnucene.2016.09.003
    [19] Komlev A, Almjashev V, Bechta S, et al. (2015) New sacrificial material for ex-vessel core catcher. J Nucl Mater 467: 778–784. https://doi.org/10.1016/j.jnucmat.2015.10.035 doi: 10.1016/j.jnucmat.2015.10.035
    [20] Morozov A, Remizov O (2012) Severe Accidents at NPPs with WWER: Scenarios, Core Degradation Processes, Control Methods: Textbook, Obninsk: National Research Nuclear University MEPHI, 90–93. Available from: https://elib.biblioatom.ru/text/morozov_tyazhelye-avarii-na-aes_2012/p0/.
    [21] Bekmuldin М, Skakov М, Baklanov V, et al. (2021) Heat-resistant composite coating with a fluidized bed of the under-reactor core catcher of a light-water nuclear reactor. Eurasian Phys Tech J 18: 65–70. https://doi.org/10.31489/2021No3/65-70 doi: 10.31489/2021No3/65-70
    [22] Nazarbayev N, Shkolnik V, Batyrbekov E, et al. (2017) Scientific, Technical and Engineering Work to Ensure the Safety of the Former Semipalatinsk Test Site, London: Worldwide Promedia, 3: 296–298.
    [23] Vurim A, Mukhamedova N, Baklanova Y, et al. (2022) Information and analytical system for processing of research results to justify the safety of atomic energy. Appl Sci 12: 9705. https://doi.org/10.3390/app12199705 doi: 10.3390/app12199705
    [24] Skakov М, Toleubekov K, Baklanov V, et al. (2022) The method of corium cooling in a core catcher of a light-water nuclear reactor. Eurasian Phys Tech J 19: 69–77. https://doi.org/10.31489/2022No3/69-77 doi: 10.31489/2022No3/69-77
    [25] Skakov M, Baklanov V, Akaev A, et al. (2023) On the possibility of forming a corium pool by induction heating in a core catcher of the Lava-B facility. Appl Sci 13: 2480. https://doi.org/10.3390/app13042480 doi: 10.3390/app13042480
    [26] Kato M, Nagasaka H, Vasilyev Y, et al. (2000) COTELS fuel coolant interaction tests under ex-vessel conditions. Proceedings of the JAERI-Conference, 36–42.
    [27] Bekmuldin M, Skakov M, Baklanov V, et al. (2023) Experimental simulation of decay heat of corium at the Lava-B test-bench. Nucl Technol 210: 46–54 https://doi.org/10.1080/00295450.2023.2226539 doi: 10.1080/00295450.2023.2226539
  • Reader Comments
  • © 2024 the Author(s), licensee AIMS Press. This is an open access article distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0)
通讯作者: 陈斌, bchen63@163.com
  • 1. 

    沈阳化工大学材料科学与工程学院 沈阳 110142

  1. 本站搜索
  2. 百度学术搜索
  3. 万方数据库搜索
  4. CNKI搜索

Metrics

Article views(1140) PDF downloads(120) Cited by(0)

Article outline

Figures and Tables

Figures(10)

/

DownLoad:  Full-Size Img  PowerPoint
Return
Return

Catalog