Advance Search
Volume 44 Issue 6
Dec.  2023
Turn off MathJax
Article Contents
Xia Bangyang, Xu Can, Qin Tianjiao, Li Qing. Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core[J]. Nuclear Power Engineering, 2023, 44(6): 260-265. doi: 10.13832/j.jnpe.2023.06.0260
Citation: Xia Bangyang, Xu Can, Qin Tianjiao, Li Qing. Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core[J]. Nuclear Power Engineering, 2023, 44(6): 260-265. doi: 10.13832/j.jnpe.2023.06.0260

Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core

doi: 10.13832/j.jnpe.2023.06.0260
  • Received Date: 2023-05-05
  • Rev Recd Date: 2023-08-20
  • Publish Date: 2023-12-15
  • Lead-cooled fast reactor system is simple with natural safety, and it is one of the Generation Ⅳ nuclear power reactors with the most development potential and reality. Due to the high density, high operating temperature and opacity of lead coolant, the core refueling process is very difficult, complex and time-consuming, which affects the economy and safety of nuclear power plants. Therefor, increasing the core cycle length and reducing the refueling frequency have become an important aspect of the design and research of large-scale commercial lead-cooled fast reactor. Based on the engineering requirements, this paper analyzes the influence laws of the factors such as nuclear fuel type, fuel element and assembly form, reflector material, control rod layout, and the setting method of fissile nuclides blanket zone on the cycle length of lead-cooled fast reactor, and establishes the loading method of long-cycle core of lead-cooled fast reactor, which provides reference for the optimization of physical design of large commercial lead-cooled fast reactor.

     

  • loading
  • [1]
    CINOTTI L, SMITH C F, SEKIMOTO H. Lead-cooled fast reactor (LFR) overview and perspectives: LLNL-CONF-414708[R]. Livermore: Lawrence Livermore National Laboratory, 2009.
    [2]
    CINOTTI L, SMITH C F, ARTIOLI C, et al. Lead-cooled fast reactor (LFR) design: safety, neutronics, thermal hydraulics, structural mechanics, fuel, core, and plant design[M]. New York: Springer, 2010: 2749-2840.
    [3]
    肖宏才. 自然安全的BREST铅冷快堆——现代核能体系中最具发展潜力的堆型[J]. 核科学与工程,2015,35(3):395-406. doi: 10.3969/j.issn.0258-0918.2015.03.001
    [4]
    TOSHINSKY G I, DEDUL A V, KOMLEV O G, et al. Lead-bismuth and lead as coolants for fast reactors[J]. World Journal of Nuclear Science and Technology, 2020, 10(2): 65-75. doi: 10.4236/wjnst.2020.102007
    [5]
    戎利建,张玉妥,陆善平,等. 铅与铅铋共晶合金手册[M]. 北京:科学出版社,2014: 23-25.
    [6]
    GLAZOV A G, LEONOV V N, ORLOV V V, et al. Brest reactor and plant-site nuclear fuel cycle[J]. Atomic Energy, 2007, 103(1): 501-508. doi: 10.1007/s10512-007-0080-5
    [7]
    HONG S G, HYUN H, YOU W. Ultra-long-life fast reactor cores having axial blanket-driver-blanket Burnup strategy with thorium and PWR spent fuels[J]. Transactions of the American Nuclear Society, 2016, 115: 1321-1323.
    [8]
    JUÁREZ-MARTÍNEZ L C, FRANÇOIS J L. Study on the use of thorium in a lead-cooled fast reactor[J]. Transactions of the American Nuclear Society, 2017, 117: 1273-1277.
    [9]
    CINOTTI L, GRASSO G, AGOSTINI P. Flexibility of the LFR: an ASSET for novel, affordable LFR-AS-200-based SMRs[J]. Transactions of the American Nuclear Society, 2017, 117: 1464-1467.
    [10]
    BAI M Q, LINDLEY B A, ABRAM T. Fuel options for nuclear ship reactors featuring reactivity swing below one dollar[J]. Nuclear Engineering and Design, 2020, 360: 110494. doi: 10.1016/j.nucengdes.2019.110494
    [11]
    ALEMBERTI A, CARLSSON J, MALAMBU E, et al. European lead fast reactor—ELSY[J]. Nuclear Engineering and Design, 2011, 241(9): 3470-3480. doi: 10.1016/j.nucengdes.2011.03.029
    [12]
    刘紫静,赵鹏程,任广益,等. 长寿命小型自然循环铅基快堆燃料选型[J]. 原子能科学技术,2020,54(5):944-953. doi: 10.7538/yzk.2019.youxian.0402
    [13]
    胡赟,徐銤. 快堆金属燃料的发展[J]. 原子能科学技术,2008,42(9):810-815.
    [14]
    郭奇勋,李宁. 快堆燃料循环与金属燃料[J]. 厦门大学学报(自然科学版),2015, 54(5): 593-602.
    [15]
    PORTER D L, CHICHESTER H J M, MEDVEDEV P G, et al. Performance of low smeared density sodium-cooled fast reactor metal fuel[J]. Journal of Nuclear Materials, 2015, 465: 464-470. doi: 10.1016/j.jnucmat.2015.06.014
    [16]
    张翔,潘小强,刘超红,等. U-Zr合金燃料与铅、铋及其合金静态相容性研究[J]. 核技术,2019,42(3):030603. doi: 10.11889/j.0253-3219.2019.hjs.42.030603
    [17]
    ADAMOV E O, KAPLIENKO A V, ORLOV V V, et al. Brest lead-cooled fast reactor: from concept to technological implementation[J]. Atomic Energy, 2021, 129(4): 179-187. doi: 10.1007/s10512-021-00731-w
    [18]
    ZABUDKO L M, GRACHEV A F, ZHEREBTSOV A A, et al. Status on performance study of mixed nitride fuel pins of BREST reactor type[J]. Nuclear Engineering and Design, 2021, 384: 111430. doi: 10.1016/j.nucengdes.2021.111430
    [19]
    李泽华,徐銤. 快堆物理基础[M]. 武汉:长江文艺出版社,2011: 7-10.
    [20]
    SMIRNOV V S. Safety features of a power unit with the BREST-OD-300 reactor[C]//International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenario. Paris, France: IAEA, 2012.
    [21]
    MOISEEV A V. Pilot demonstration reactor BREST-OD-300: conceptual approaches and their implementation[C]//9th Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors. Vienna, Austria: IAEA, 2021.
    [22]
    秦天骄,夏榜样,李晴,等. 铅冷行波堆反应性变化规律及其影响因素研究[J]. 核动力工程,2022,43(4):206-212.
    [23]
    HEJZLAR P, PETROSKI R, CHEATHAM J, et al. Terrapower, LLC traveling wave reactor development program overview[J]. Nuclear Engineering and Technology, 2013, 45(6): 731-744. doi: 10.5516/NET.02.2013.520
    [24]
    WANG K, LI Z G, SHE D, et al. RMC – A Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 2015, 82: 121-129. doi: 10.1016/j.anucene.2014.08.048
  • 加载中

Catalog

    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

    Figures(6)  / Tables(1)

    Article Metrics

    Article views (1990) PDF downloads(90) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return