Effects of forging and heat treatments on stress corrosion behavior of 316ln stainless steel in high temperature caustic solution

被引:0
|
作者
Guo, Yueling [1 ,2 ]
Han, En-Hou [1 ,2 ]
Wang, Jianqiu [2 ]
机构
[1] National Center for Materials Service Safety, University of Science and Technology Beijing, Beijing,100083, China
[2] Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Science, Shenyang,110016, China
来源
关键词
Nuclear fuels - Textures - Crack propagation - Forging - Nuclear power plants - Residual stresses - Austenitic stainless steel - Morphology - Corrosive effects - Nuclear energy - Crack tips - Pressurized water reactors - Steel corrosion - Grain size and shape - Intergranular corrosion - Grain boundaries - Heat treatment - Coolants;
D O I
10.11900/0412.1961.2014.00466
中图分类号
学科分类号
摘要
The reactor coolant piping in the third generation nuclear power plants of AP1000 is manufactured by integrally forging. Therefore, it is of vital importance to investigate the effects of forging and heat treatments on the stress corrosion cracking (SCC) resistance of 316LN stainless steel (316LNSS), which is the candidate material for the reactor coolant piping in AP1000 nuclear power plants. In this work, electron back scattering diffraction (EBSD) and microhardness measurements (HV) were used to characterize the microstructure and residual strain of the as-received 316LNSS, the forged and solution anneal treated 316LNSS and the forged and stress relief treated 316LNSS, respectively. The average grain size of the as-received 316LNSS was the largest, and the forged 316LNSS followed by solution anneal treatment and stress relief treatment showed no obvious differences on grain size. The as-received 316LNSS exhibited the highest residual strain followed by the forged and stress relief treated 316LNSS and then solution anneal treated 316LNSS. Besides, the residual strain in the as-received 316LNSS concentrated on grain boundaries, while the residual strain in the forged and stress relief treated 316LNSS was characterized by a band-like distribution. The U-bend specimens were utilized to investigate the SCC behavior of the 3 kinds of 316LNSS specimens in high temperature caustic solution. After SCC experiments, the crack morphologies of the 3 kinds of 316LNSS specimens were examined by SEM. Then the macro and micro fracture morphologies were examined by OM and SEM, respectively. Grain morphology, residual strain and grain boundary character distribution near the SCC crack tip of the forged and stress relief treated 316LNSS were investigated using EBSD. The results showed that the forged and solution anneal treated 316LNSS exhibited the lowest SCC sensibility, while the as-received the highest, with the most cracks and the highest growth rate. The as-received and the forged and solution anneal treated 316LNSS showed obvious intergranular cracking, while the forged and stress relief treated 316LNSS showed a mixed cracking mode. The larger average grain size and higher residual strain, especially concentrating on the grain boundaries, were considered to be responsible for the highest SCC sensibility of the as-received 316LNSS. Compared with the forged and stress relief treated 316LNSS, the higher content of coincidence site lattice boundary (CSLB) and lower residual strain contributed to the lower SCC sensibility of forged and solution anneal treated 316LNSS. The stress relief treatment failed to eliminate the band-like microstructure effectively, which disadvantaged the SCC resistance. © All right reserved.
引用
收藏
页码:659 / 667
相关论文
共 50 条
  • [31] Static Recrystallization Behavior of 316LN Austenitic Stainless Steel
    JIN Miao
    LU Bo
    LIU Xin-gang
    GUO Huan
    JI Hai-peng
    GUO Bao-feng
    Journal of Iron and Steel Research(International), 2013, 20 (11) : 67 - 72
  • [32] Microstructure in 316LN stainless steel fatigued at low temperature
    Kruml, T
    Polák, J
    Degallaix, S
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2000, 293 (1-2): : 275 - 280
  • [33] Static Recrystallization Behavior of 316LN Austenitic Stainless Steel
    Miao Jin
    Bo Lu
    Xin-gang Liu
    Huan Guo
    Hai-peng Ji
    Bao-feng Guo
    Journal of Iron and Steel Research International, 2013, 20 : 67 - 72
  • [34] THE CORROSION FATIGUE CRACK PROPAGATION OF 316LN AUSTENITIC STAINLESS STEEL
    Yang, Bin
    Wu, Huanchun
    7TH INTERNATIONAL CONFERENCE INTEGRITY-RELIABILITY-FAILURE (IRF2020), 2020, : 321 - 322
  • [35] Stress Corrosion Behaviors of 316LN Stainless Steel in a Simulated PWR Primary Water Environment
    Huang, Yong
    Wu, Weisong
    Cong, Shuo
    Ran, Guang
    Cen, Danxia
    Li, Ning
    MATERIALS, 2018, 11 (09)
  • [36] Stress corrosion cracking of AISI 316LN stainless steel in ITER primary water conditions
    Lorenzetto, P
    Helie, M
    Molander, A
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 1387 - 1392
  • [37] Effect of grain boundary engineering on corrosion fatigue behavior of 316LN stainless steel in borated and lithiated high-temperature water
    Gao, Jun
    Tan, Jibo
    Wu, Xinqiang
    Xia, Shuang
    CORROSION SCIENCE, 2019, 152 : 190 - 201
  • [38] Effects of dwell time on the isothermal and thermomechanical fatigue behavior of 316LN stainless steel
    Zhao, Jingwei
    Li, Bingbing
    Chen, Gang
    Itoh, Takamoto
    Chen, Xu
    INTERNATIONAL JOURNAL OF FATIGUE, 2022, 162
  • [39] Investigations on corrosion behavior of 316LN and 316L austenitic stainless steel under corrosion-deformation interactions
    Rao, Sixian
    Zhang, Changwei
    Zhao, Fei
    Bao, Lei
    Wang, Xiaoyi
    ANTI-CORROSION METHODS AND MATERIALS, 2024, 71 (04) : 357 - 367
  • [40] Effects of temperature on ratchetting behavior and cracking mechanism of 316LN stainless steel in different temperature pressured water environments
    Hong, C.
    Lu, S. L. .
    Zhao, Y. G.
    Li, Z. H.
    Lu, Y. H.
    CORROSION SCIENCE, 2025, 249