Structure of surface oxides on martensitic steel under simultaneous ion irradiation and molten LBE corrosion

被引:41
作者
Yao, Cunfeng [1 ,2 ]
Zhang, Hongpeng [1 ,2 ]
Chang, Hailong [1 ,2 ]
Sheng, Yanbin [1 ,2 ]
Shen, Tielong [1 ,2 ]
Zhu, Yabin [1 ,2 ]
Pang, Lilong [1 ,2 ]
Cui, Minghuan [1 ,2 ]
Wei, Kongfang [1 ,2 ]
Xu, Yichun [3 ]
Wang, Dong [4 ]
Liu, Chao [1 ,2 ]
Ma, Zhiwei [1 ,2 ]
Zhao, Li [1 ,2 ]
Yan, Wei [5 ]
Peng, Tianji [1 ,2 ]
Li, Jinyang [1 ,2 ]
Qin, Changping [1 ,2 ]
Wang, Zhiguang [1 ,2 ]
机构
[1] Chinese Acad Sci, Inst Modern Phys, Lanzhou 73000, Peoples R China
[2] Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China
[3] Chinese Acad Sci, Inst Solid State Phys, Key Lab Mat Phys, Hefei 230031, Peoples R China
[4] Nucl Power Inst China, Sci & Technol Reactor Fuel & Mat Lab, Chengdu 610200, Peoples R China
[5] Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
基金
中国国家自然科学基金;
关键词
Martensitic steel; Liquid LBE; Irradiation damage; Synergistic effect; GLASS TRANSFORMATION; STAINLESS-STEEL; LEAD; OXIDATION; CRYSTAL; TEMPERATURE; MICROSCOPY; RESISTANCE; DIFFUSION; BEHAVIOR;
D O I
10.1016/j.corsci.2021.109953
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Irradiation damage on corrosion process of steels in Pb or LBE melts is a main challenge for the R&D of LFR. In this paper, A martensitic steel (SIMP) was in-situ irradiated with 247 MeV Ar ions while simultaneously exposed to flowing molten LBE to investigate the effect of irradiation on the structure of surface oxides. The results showed that ion irradiation not only accelerated the LBE corrosion, but also modified the structure of surface oxides significantly. Possible mechanism was proposed to help understand the microstructure evolution of oxides under simultaneous irradiation and corrosion.
引用
收藏
页数:13
相关论文
共 64 条
  • [1] MYRRHA - A multi-purpose fast spectrum research reactor
    Abderrahim, Hamid Ait
    Baeten, Peter
    De Bruyn, Didier
    Fernandez, Rafael
    [J]. ENERGY CONVERSION AND MANAGEMENT, 2012, 63 : 4 - 10
  • [2] ASPECTS OF SIMULATION OF NEUTRON DAMAGE BY ION IRRADIATION
    ABROMEIT, C
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 216 : 78 - 96
  • [3] Overview of lead-cooled fast reactor activities
    Alemberti, Alessandro
    Smirnov, Valery
    Smith, Craig F.
    Takahashi, Minoru
    [J]. PROGRESS IN NUCLEAR ENERGY, 2014, 77 : 300 - 307
  • [4] A MODEL FOR WATERSIDE OXIDATION OF ZIRCALOY FUEL CLADDING IN PRESSURIZED WATER-REACTORS
    ALMARSHAD, AIA
    KLEIN, AC
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1991, 183 (03) : 186 - 194
  • [5] [Anonymous], 1975, PHASE DIAGRAMS CERAM
  • [6] [Anonymous], 2015, Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies
  • [7] [Anonymous], 1979, Metallurgical Thermochemistry
  • [8] [Anonymous], CORROSION FUNDAMENTA, V13A
  • [9] A THEORETICAL-ANALYSIS OF THE OXIDATION OF FE-SI ALLOYS
    ATKINSON, A
    [J]. CORROSION SCIENCE, 1982, 22 (02) : 87 - 102
  • [10] Corrosion behavior of steels in flowing lead-bismuth
    Barbier, F
    Rusanov, A
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2001, 296 : 231 - 236