ISSN 0253-2778

CN 34-1054/N

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Simulating method of sodium-water reaction accident in steam generator of sodium-cooled fast reactor

  • 1.

    School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 260026, China

  • 2.

    Research Institute of Nuclear Power Operation,China National Nuclear Corporation, Wuhan 430074, China

Cite this:
https://doi.org/10.3969/j.issn.0253-2778.2020.04.006
  • Received Date: 01 April 2019
  • Accepted Date: 22 May 2019
  • Rev Recd Date: 22 May 2019
  • Publish Date: 30 April 2020
    Abstract

  • Abstract

    The simulation of sodium-water reaction accident is the difficulty in the development of the simulating system of sodium cooled reactor. In order to solve this problem, a simulation program of sodium-water reaction accident was designed based on the mathematical physical equation of sodium-water reaction accident caused by water leakage in heat transfer tube of sodium-cooled fast reactor steam generator. Based on SimTherm thermal-hydraulic simulation program and the structure of sodium-cooled fast reactor, a second-circuit model of sodium-cooled fast reactor was designed for the study of sodium-water reaction accidents. By coupling the simulation program of sodium-water reaction accident with SimTherm, the simulation of sodium-water reaction accident was realized, which provides a new idea for the development of sodium-cooled fast reactor simulator.

    Abstract

    The simulation of sodium-water reaction accident is the difficulty in the development of the simulating system of sodium cooled reactor. In order to solve this problem, a simulation program of sodium-water reaction accident was designed based on the mathematical physical equation of sodium-water reaction accident caused by water leakage in heat transfer tube of sodium-cooled fast reactor steam generator. Based on SimTherm thermal-hydraulic simulation program and the structure of sodium-cooled fast reactor, a second-circuit model of sodium-cooled fast reactor was designed for the study of sodium-water reaction accidents. By coupling the simulation program of sodium-water reaction accident with SimTherm, the simulation of sodium-water reaction accident was realized, which provides a new idea for the development of sodium-cooled fast reactor simulator.
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    • References(18)
  • [1]
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    刘晓宇. 快堆中间回路钠水反应事故仿真[D]. 哈尔滨: 哈尔滨工程大学, 2012.
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    PERKINS T K. Critical and subcritical flow of multiphase mixtures through chokes[J]. SPE Drilling & Completion, 1993, 8(4): 271-276.
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    翁方检. 快堆蒸汽发生器大钠水反应事故研究[D]. 北京: 中国原子能科学研究院, 2005.
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    TAKASHI T, AKIRA Y. Numerical thermal-hydraulics study on sodium-water reaction phenomena[J]. 2003.
    [14]
    SHIN Y W. Method of characteristics for analysis of pressure transients resulting from sodium-water reaction in hydraulic networks[R].Lemont, IL: Argonne National Laboratory, 1973.
    [15]
    HILGENFELDT S, BRENNER M P, GROSSMANN S, et al. Analysis of Rayleigh-Plesset dynamics for sonoluminescing bubbles[J]. Journal of Fluid Mechanics, 1998, 365: 171-204.
    [16]
    OSHKANOV N N, BAKANOV M V, POTAPOV O A. Experience in operating the BN-600 unit at the Belyi Yar Nuclear Power Plant[J]. Atomic Energy, 2004, 96(5): 315-319.
    [17]
    GOTTLIEB S, SHU C W. Total variation diminishing Runge-Kutta schemes[J]. Mathematics of Computation of the American Mathematical Society, 1998, 67(221): 73-85.
    [18]
    张东辉, 任丽霞. 中国实验快堆系列丛书：快堆安全分析[M].北京：中国原子能科学院, 2011.)
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    [1]
    宋维, 杨红义. 中国示范快堆总体技术预先研究进展[J]. 中国原子能科学研究院年报, 2011(1): 5.
    [2]
    BUKSHA Y K, BAGDASSAROV Y E, KIRYUSHIN A I, et al. Operation experience of the BN-600 fast reactor[J]. Nuclear Engineering and Design, 1997, 173(1): 67-79.
    [3]
    沈莲, 王秀苓, 马丽华, 等. 奥氏体不锈钢在高温钠中的质量迁移效应研究[J]. 西安交通大学学报, 1991, 25(6): 79-88.
    SHEN Lian, WANG Xiuling, MA Lihua, et al. Study of mass transfer behaviors in austenitic stainless steels exposed to sodium at high temperature[J]. Journal of Xi'an Jiaotong University, 1991, 25(6): 79-88.
    [4]
    UCHIYAMA N, TAKAI T, NISHIMURA M, et al. Investigation for the sodium leak Monju. Sodium fire test-II[R]. Ibaraki, Jpn: Japan Nuclear Cycle Development Institute, 2000.
    [5]
    JAMES L A, KNECHT R L. Fatigue-crack propagation behavior of type 304 stainless steel in a liquid sodium environment[J]. Metallurgical Transactions A, 1975, 6(1): 109-116.
    [6]
    王洲, 杨翔. 大泄漏钠水反应引起压力波传播的研究[J]. 核科学与工程, 1997, 17(1): 21-30.
    WANG Zhou, YANG Xiang. Study of pressure wave propagation resulting from large leak sodium-water reactions[J]. Chinese Journal of Nuclear Science and Engineering, 1997, 17(1): 21-30.
    [7]
    沙仁礼. 钠水反应试验研究概况及进展[J]. 原子能科学技术, 1990, 24(3): 76-86.
    SHA Renli. Status and development of experimental study on sodium water reactor[J]. Atomic Energy Science and Technology, 1990, 24(3): 76-86.
    [8]
    骆炎, 张建民, 单建强, 等. 快堆蒸汽发生器大泄漏钠水反应计算[J]. 核科学与工程, 2000, 20(2): 154-161.
    LUO Yan, ZHANG Jianmin, SHAN Jianqiang, et al. Calculation of large leak sodium/water reaction in steam generator of LMFBR[J]. Chinese Journal of Nuclear Science and Engineering, 2000, 20(2): 154-161.
    [9]
    刘晓宇. 快堆中间回路钠水反应事故仿真[D]. 哈尔滨: 哈尔滨工程大学, 2012.
    [10]
    PERKINS T K. Critical and subcritical flow of multiphase mixtures through chokes[J]. SPE Drilling & Completion, 1993, 8(4): 271-276.
    [11]
    翁方检. 快堆蒸汽发生器大钠水反应事故研究[D]. 北京: 中国原子能科学研究院, 2005.
    [12]
    段日强, 杨献勇, 王洲. 液态钠-氢系统化学热力学平衡分析[J]. 原子能科学技术, 2000, 34(1): 76-80.
    DUAN Riqiang, YANG Xianyong, WANG Zhou. Study of chemical thermodynamic equilibrium of liquid sodium-hydrogen system[J]. Atomic Energy Science and Technology, 2000, 34(1): 76-80.
    [13]
    TAKASHI T, AKIRA Y. Numerical thermal-hydraulics study on sodium-water reaction phenomena[J]. 2003.
    [14]
    SHIN Y W. Method of characteristics for analysis of pressure transients resulting from sodium-water reaction in hydraulic networks[R].Lemont, IL: Argonne National Laboratory, 1973.
    [15]
    HILGENFELDT S, BRENNER M P, GROSSMANN S, et al. Analysis of Rayleigh-Plesset dynamics for sonoluminescing bubbles[J]. Journal of Fluid Mechanics, 1998, 365: 171-204.
    [16]
    OSHKANOV N N, BAKANOV M V, POTAPOV O A. Experience in operating the BN-600 unit at the Belyi Yar Nuclear Power Plant[J]. Atomic Energy, 2004, 96(5): 315-319.
    [17]
    GOTTLIEB S, SHU C W. Total variation diminishing Runge-Kutta schemes[J]. Mathematics of Computation of the American Mathematical Society, 1998, 67(221): 73-85.
    [18]
    张东辉, 任丽霞. 中国实验快堆系列丛书：快堆安全分析[M].北京：中国原子能科学院, 2011.)
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