Technical Note: Corrosion Fatigue Crack Growth of Forged Type 316NG Austenitic Stainless Steel in 325°C Water

被引:6
|
作者
Xiao, J. [1 ]
Chen, L. Y. [1 ]
Zhou, J. [1 ]
Qiu, S. Y. [1 ]
Chen, Y. [1 ]
机构
[1] Nucl Power Inst China, Sci & Technol Reactor Fuel & Mat Lab, Chengdu 610041, Sichuan, Peoples R China
关键词
fatigue crack growth; pressurized water reactor; primary coolant pipe; Type 316NG austenitic stainless steel; LOW-CYCLE FATIGUE; TEMPERATURE; BEHAVIOR; LIFE; ENVIRONMENTS; MECHANISMS; INITIATION; DEFLECTION; PRESSURE;
D O I
10.5006/2647
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Forged Type 316NG austenitic stainless steel is commonly used to fabricate primary coolant pipe in advanced pressurized water reactor systems, but it is subject to corrosion fatigue cracking in primary coolant environments. In this study, the fatigue crack growth of Type 316NG austenitic stainless steel in 325 degrees C water was investigated. The corrosion fatigue effect in 325 degrees C water was mainly correlated to the crack growth rate and load frequency. A maximum F-en (environment corrected factor) value up to 100 was observed at f = 0.005 Hz, Delta K = 13 MPa root m. The dissolved oxygen tended to have little influence on the fatigue crack growth. The crack path was deflected and branched. Most secondary cracks tended to be initiated from grain boundaries.
引用
收藏
页码:387 / 392
页数:6
相关论文
共 50 条
  • [1] Fatigue crack growth of 316NG austenitic stainless steel welds at 325 °C
    Li, Y. F.
    Xiao, J.
    Chen, Y.
    Zhou, J.
    Qiu, S. Y.
    Xu, Q.
    JOURNAL OF NUCLEAR MATERIALS, 2018, 499 : 353 - 360
  • [2] Effect of Predeformation on Corrosion Fatigue Crack Growth of Type 316NG Steel in 325°C Deaerated Water
    Xiao, Jun
    Zheng, Yu Qi
    Xiao, Ting
    Wang, Hao
    Xu, Qi
    CORROSION, 2025, 81 (02)
  • [3] Effect of heat treatment on fatigue crack growth behavior of 316NG austenitic stainless steel in deaerated water at 325 °C
    Xiao, Jun
    Zheng, Yu Qi
    Xiao, Ting
    Wang, Hao
    Chen, Yong
    Qiu, Shao Yu
    Gong, Xing
    JOURNAL OF NUCLEAR MATERIALS, 2021, 557
  • [4] Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water
    Dong, Lijin
    Peng, Qunjia
    Zhang, Zhiming
    Shoji, Tetsuo
    Han, En-Hou
    Ke, Wei
    Wang, Lei
    NUCLEAR ENGINEERING AND DESIGN, 2015, 295 : 403 - 414
  • [5] Fatigue life and crack growth mechanisms of the type 316LN austenitic Stainless Steel in 310°C deoxygenated water
    Cho, Hyunchul
    Kim, Byoung Koo
    Kim, In Sup
    Jang, Changheui
    Jung, Dae Yul
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2007, 44 (07) : 1007 - 1014
  • [6] THE CORROSION FATIGUE CRACK PROPAGATION OF 316LN AUSTENITIC STAINLESS STEEL
    Yang, Bin
    Wu, Huanchun
    7TH INTERNATIONAL CONFERENCE INTEGRITY-RELIABILITY-FAILURE (IRF2020), 2020, : 321 - 322
  • [7] Corrosion fatigue crack growth behavior of 316NG heat affected zone in simulated pressurized water reactor environment
    Xiao, Jun
    Xiao, Ting
    Zheng, Yuqi
    Wang, Hao
    Chen, Yong
    Qiu, Shaoyu
    Gong, Xing
    JOURNAL OF NUCLEAR MATERIALS, 2020, 537
  • [8] Stress corrosion crack growth in type 316 stainless steel in Supercritical water
    Peng, Q. J.
    Teysseyre, S.
    Andresen, P. L.
    Was, G. S.
    CORROSION, 2007, 63 (11) : 1033 - 1041
  • [9] Role of δ-ferrite in fatigue crack growth of AISI 316 austenitic stainless steel
    Qiyu Wang
    Shenghu Chen
    Xinliang Lv
    Haichang Jiang
    Lijian Rong
    Journal of Materials Science & Technology, 2022, 114 (19) : 7 - 15
  • [10] Role of δ-ferrite in fatigue crack growth of AISI 316 austenitic stainless steel
    Wang, Qiyu
    Chen, Shenghu
    Lv, Xinliang
    Jiang, Haichang
    Rong, Lijian
    JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 114 : 7 - 15