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CN 34-1054/N

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Effects of corrosion on tensile property of 316L fiber felt in lead bismuth eutectic

  • 1.

    Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China

  • 2.

    School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027, China

Cite this:
https://doi.org/10.3969/j.issn.0253-2778.2017.06.006
  • Received Date: 01 December 2016
  • Rev Recd Date: 21 April 2017
  • Publish Date: 30 June 2017
    Abstract

  • Abstract

    Based on the operation environment of China Lead-based Research Reactor (CLEAR-I), the tensile properties of filter material-sintered 316L fiber felt exposed to stagnant lead bismuth eutectic (LBE) with 1×10-6 wt% oxygen concentration was investigated at 500℃ for 500 h, 1000h, 1500 h. The results showed that compared to the original fiber felt, the tensile strength of the fiber felts decreased to 67%, 33% and 15% after 500 h, 1000 h and 1500 h, respectively. It was found that the binding strength of the joints and diameter of 316L stainless steel fibers gradually decreased with exposure time due to the compact single-layer (Fe,Cr)3O4 spinel formation on 316L fibers, which was the main cause of tensile strength of sintered 316L fiber felt dropping after LBE corrosion.

    Abstract

    Based on the operation environment of China Lead-based Research Reactor (CLEAR-I), the tensile properties of filter material-sintered 316L fiber felt exposed to stagnant lead bismuth eutectic (LBE) with 1×10-6 wt% oxygen concentration was investigated at 500℃ for 500 h, 1000h, 1500 h. The results showed that compared to the original fiber felt, the tensile strength of the fiber felts decreased to 67%, 33% and 15% after 500 h, 1000 h and 1500 h, respectively. It was found that the binding strength of the joints and diameter of 316L stainless steel fibers gradually decreased with exposure time due to the compact single-layer (Fe,Cr)3O4 spinel formation on 316L fibers, which was the main cause of tensile strength of sintered 316L fiber felt dropping after LBE corrosion.
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    • References(29)
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    田书建，张建武. 316L和T91不锈钢在550℃静态铅铋合金中的腐蚀行为[J]. 中国科学技术大学学报，2015, 45(9):751-756.
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    [28]
    钱余海，李美栓，张亚明. 氧化膜开裂和剥落行为[J]. 腐蚀科学与防护技术，2003，15(2):90-93.
    QIAN Yuhai, LI Meishuan, ZHANG Yaming. Cracking and spalling behavior of thin oxide scale[J]. Corrosion Science and Protection Technology, 2003，15(2):90-93.
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    LIU Dabiao, HE Yuming, HU Peng, et al. On the mechanical properties in micro-tensile testing of single fiber[J]. Journal of Experimental Mechanics, 2012，27(1):61-69.
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    [1]
    OECD Nuclear Energy Agency for the Generation IV International Forum. Technology Roadmap Update for Generation IV Nuclear Energy Systems[R/OL]. [2016-09-10] https://www.gen-4.org/gif/upload/docs/application/pdf/2014-03/gif-tru2014.pdf.
    [2]
    ALEMBERTI A, SMIRNOV V, SMITH C F, et al. Overview of lead-cooled fast reactor activities[J]. Progress in Nuclear Energy, 2014, 77: 300-307.
    [3]
    MARTYNOV P N, ASKHADULLIN R SH, ORLOV YUI, et al. Modern problems and tasks of modern heavy liquid metal coolant technology (lead, lead-bismuth)[C]// IV Conference “Heavy Liquid Metal Coolants in Nuclear Technologies” HLMC-2013, Obninsk, Russia, 2013.
    [4]
    COUROUAU J L, SELLIER S, BALBAUD F, et al. Initial start-up operations chemistry analysis for MEGAPIE[C]// Proceedings of the 5th MEGAPIE Technical Review Meeting, Nantes, France, 2004.
    [5]
    ZRODNIKOV A V, EFANOV A D, ORLOV Y I, et al. Heavy liquid metal coolant-lead-bismuth and lead-technology[J]. Atomic Energy, 2004, 97(2): 534-537.
    [6]
    PURCHAS D B, SUTHERLAND K. Handbook of Filter Media[M]. New York: Elsevier, 2002.
    [7]
    QINGBO A, HUIPING T, JIANZHONGW, et al. Corrosion behavior of sintered 316L stainless steel fiber porous felt[J]. Rare Metal Materials and Engineering, 2014, 43(10): 2344-2348.
    [8]
    MARTYNOV P N, YAGODKIN I V, ASKHADULLIN R Sh, et al. Filtration purification of heavy liquid metal coolants from impurities[C]// IV Conference “Heavy Liquid Metal Coolants in Nuclear Technologies” HLMC-2013, Obninsk, Russia, 2013.
    [9]
    BEAUCHAMP F, MORIER O, BRISSONNEAU L, Et al. A review of lead-bismuth alloy purification systems with regard to the latest results achieved on STELLA loop[C]// Technology and Components of Accelerator-driven Systems Workshop Proceedings, Karlsruhe, Germany, 2010.
    [10]
    VAN DEN BOSCH J, AERTS A, LIMJ, et al . Overview of the LBE chemistry, conditioning and purification program at SCK-CEN[C]// IV Conference “Heavy Liquid Metal Coolants in Nuclear Technologies” HLMC-2013, Obninsk, Russia, 2013.
    [11]
    ZHANG J. A review of steel corrosion by liquid lead and lead-bismuth[J]. Corrosion Science, 2009, 51(6): 1207-1227.
    [12]
    WU Y, FDS Team. Conceptual design activities of FDS series fusion power plants in China[J]. Fusion Engineering and Design, 2006, 81(23): 2713-2718.
    [13]
    WU Y, FDS Team. CAD-based interface programs for fusion neutron transport simulation[J]. Fusion Engineering and Design, 2009, 84(7): 1987-1992.
    [14]
    WU Y, FDS Team. Conceptual design and testing strategy of a dual functional lithium-lead test blanket module in ITER and EAST[J]. Nuclear Fusion, 2007, 47(11): 1533.
    [15]
    WU Y, FDS Team. Development of reliability and probabilistic safety assessment program RiskA[J]. Annals of Nuclear Energy, 2015, 83: 316-321.
    [16]
    WU Y, SONG G, WANG Y, et al. Development of high intensity D-T fusion neutron generator HINEG[J]. International Journal of Energy Research, 2016: DOI: 10.1002/er.3572.
    [17]
    HUANG Q, FDS Team. Development status of CLAM steel for fusion application[J]. Journal of Nuclear Materials, 2014, 455(1): 649-654.
    [18]
    WU Y, SONG J, ZHENG H, et al. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC[J]. Annals of Nuclear Energy, 2015, 82:161-168.
    [19]
    WU Y. CLEAR-S: an integrated non-nuclear test facility for China lead-based research reactor[J]. International Journal of Energy Research, 2016, 40(14): 1951-1956.
    [20]
    WU Y, XIE Z, FISCHERU. A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries[J]. Nuclear Science and Engineering, 1999, 133(3): 350-357.
    [21]
    WU Y. Design and R&D progress of China lead-based reactor for ADS research facility[J]. Engineering, 2016, 2(1): 124-131.
    [22]
    刘怀礼，王建忠，汤慧萍. 不锈钢纤维多孔材料拉伸性能研究[J]. 稀有金属材料与工程, 2014, 43(8): 2023-2026.
    LIU Huali, WANG Jianzhong, TANG Huiping. Tensile properties of stainless steel fiber porous materials[J]. Rare Metal Materials and Engineering, 2014, 43(8):2023-2026.
    [23]
    奚正平，汤慧萍. 烧结金属多孔材料(精)[M]. 北京：冶金工业出版社，2009:254-255.
    [24]
    田书建，张建武. 316L和T91不锈钢在550℃静态铅铋合金中的腐蚀行为[J]. 中国科学技术大学学报，2015, 45(9):751-756.
    TIAN Shujian, ZHANG Jianwu. Corrosion behavior of 316L and T91 steels in stagnant lead-bismuth eutectic at 550 ℃[J]. Journal of University of Science and Technology of China, 2015, 45(9):751-756.
    [25]
    FAZIO C, SOBOLEV V P, AERTSA, et al. Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies-2015 Edition[R]. Organization for Economic Co-Operation and Development, 2015.
    [26]
    李美栓. 金属的高温腐蚀[M]. 北京：冶金工业出版社，2001:196-200.
    [27]
    BO Z, WEI Y, HU J,et al. Uniaxial tensile behavior of porous metal fiber sintered sheet[J]. Transactions of Nonferrous Metals Society of China, 2015, 25(6): 2003-2008.
    [28]
    钱余海，李美栓，张亚明. 氧化膜开裂和剥落行为[J]. 腐蚀科学与防护技术，2003，15(2):90-93.
    QIAN Yuhai, LI Meishuan, ZHANG Yaming. Cracking and spalling behavior of thin oxide scale[J]. Corrosion Science and Protection Technology, 2003，15(2):90-93.
    [29]
    刘大彪，何玉明，胡鹏，等. 单纤维微拉伸力学性能测试与分析[J]. 实验力学，2012，27(1):61-69.
    LIU Dabiao, HE Yuming, HU Peng, et al. On the mechanical properties in micro-tensile testing of single fiber[J]. Journal of Experimental Mechanics, 2012，27(1):61-69.
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