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Volume 44 Issue 2
Apr.  2023
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Yang Tao, Zhao Pengcheng, Zhao Yanan, Yu Tao. Development of Reduced-Order Thermal Stratification Model for Upper Plenum of Lead-Bismuth Fast Reactor Based on CFD[J]. Nuclear Power Engineering, 2023, 44(2): 48-53. doi: 10.13832/j.jnpe.2023.02.0048
Citation: Yang Tao, Zhao Pengcheng, Zhao Yanan, Yu Tao. Development of Reduced-Order Thermal Stratification Model for Upper Plenum of Lead-Bismuth Fast Reactor Based on CFD[J]. Nuclear Power Engineering, 2023, 44(2): 48-53. doi: 10.13832/j.jnpe.2023.02.0048

Development of Reduced-Order Thermal Stratification Model for Upper Plenum of Lead-Bismuth Fast Reactor Based on CFD

doi: 10.13832/j.jnpe.2023.02.0048
  • Received Date: 2022-05-30
  • Rev Recd Date: 2023-01-19
  • Publish Date: 2023-04-15
  • After the emergency shutdown of the lead-bismuth fast reactor, the thermal stratification in the upper plenum has an important impact on the integrity of the reactor structure and the residual heat removal capacity of the natural circulation, which requires special attention. In order to overcome the defects of traditional thermal stratification analysis method, a high-precision full-order snapshot is obtained based on computational fluid dynamics (CFD) code, and a reduced-order thermal stratification model is built by combining proper orthogonal decomposition (POD) with Galerkin projection. After conducting a comparative analysis of thermal stratification with the full-order model of CFD, the results show that the reduced-order thermal stratification model developed can effectively simulate the temperature distribution in the upper plenum and carry out a quick research on the thermal stratification interface characteristics in case of the lead-bismuth fast reactor accident. The research in this paper provides an important analytical tool for studying the thermal stratification mechanism and effectively curbing the thermal stratification.

     

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  • [1]
    薛秀丽,杨红义,冯预恒. 日本文殊快堆紧急停堆后堆芯出口腔室瞬态工况模拟研究[J]. 原子能科学技术,2017, 51(10): 1827-1833. doi: 10.7538/yzk.2017.51.10.1827
    [2]
    MORIYA S, TANAKA N, KATANO N, et al. Effects of Reynolds number and Richardson number on thermal stratification in hot plenum[J]. Nuclear Engineering and Design, 1987, 99: 441-451. doi: 10.1016/0029-5493(87)90140-3
    [3]
    SCHNEIDER J A, ANDERSON M H. Thermal stratification in a pool-type geometry: DOE-UWM-10268-3[R]. Madison: University of Wisconsin Madison, 2019.
    [4]
    BANDINI G, POLIDORI M, GERSCHENFELD A, et al. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors[J]. Nuclear Engineering and Design, 2015, 281: 22-38. doi: 10.1016/j.nucengdes.2014.11.003
    [5]
    YUE N N, MA Z Y, CAI R, et al. Thermal-hydraulic analysis of EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R[J]. Progress in Nuclear Energy, 2015, 85: 682-693. doi: 10.1016/j.pnucene.2015.09.002
    [6]
    LU C H, WU Z Y, MORGAN S, et al. An efficient 1-D thermal stratification model for pool-type sodium-cooled fast reactors[J]. Nuclear Technology, 2020, 206(10): 1465-1480. doi: 10.1080/00295450.2020.1719799
    [7]
    DONG Z Y, QIU H R, WANG M J, et al. Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR)[J]. Annals of Nuclear Energy, 2022, 174: 109176. doi: 10.1016/j.anucene.2022.109176
    [8]
    HE S P, WANG M J, ZHANG J, et al. Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth[J]. Nuclear Engineering and Technology, 2021, 53(6): 1834-1845. doi: 10.1016/j.net.2020.12.025
    [9]
    WANG M J, WANG Y J, TIAN W X, et al. Recent progress of CFD applications in PWR thermal hydraulics study and future directions[J]. Annals of Nuclear Energy, 2021, 150: 107836. doi: 10.1016/j.anucene.2020.107836
    [10]
    SHIBAHARA M, TAKATA T, YAMAGUCHI A. Numerical study on thermal stratification phenomena in upper plenum of LMFBR “MONJU”[J]. Nuclear Engineering and Design, 2013, 258: 226-234. doi: 10.1016/j.nucengdes.2013.02.007
    [11]
    SCHNEIDER J, ANDERSON M, BAGLIETTO E, et al. Thermal stratification analysis for sodium fast reactors [C]//Proceedings of 2018 International Congress on Advances in Nuclear Power Plants. Charlotte, 2018.
    [12]
    ABE K, KONDOH T, NAGANO Y. A two-equation heat transfer model reflecting second-moment closures for wall and free turbulent flows[J]. International Journal of Heat and Fluid Flow, 1996, 17(3): 228-237. doi: 10.1016/0142-727X(96)00037-9
    [13]
    ABE K, KONDOH T, NAGANO Y. A new turbulence model for predicting fluid flow and heat transfer in separating and reattaching flows—I. Flow field calculations[J]. International Journal of Heat and Mass Transfer, 1994, 37(1): 139-151. doi: 10.1016/0017-9310(94)90168-6
    [14]
    FAZIO Concetta. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies-2015 edition-Introduction [M]. Paris: OECD, 2016: 17-27.
    [15]
    丁鹏,陶文铨. 建立低阶模型的POD方法[J]. 工程热物理学报,2009, 30(6): 1019-1021.
    [16]
    ROWLEY C W, COLONIUS T, MURRAY R M. Model reduction for compressible flows using POD and Galerkin projection[J]. Physica D:Nonlinear Phenomena, 2004, 189(1-2): 115-129. doi: 10.1016/j.physd.2003.03.001
    [17]
    VOLKWEIN S. Model reduction using proper orthogonal decomposition [EB/OL]. (2011-12-07). [2022-05-01]. http://www.uni-graz.at/imawww/volkwein/POD.pdf.
    [18]
    李航. 统计学习方法[M]. 北京: 清华大学出版社, 2012: 271-290.
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